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use a plain point source coming with OpenMC official is fine, as suggested by Jonathon. see the code tweak at the end.
===============> FIXED SOURCE TRANSPORT SIMULATION <===============
Simulating batch 1
WARNING: WARNING: WARNING: Could not find the cell containing particle 1
WARNING: Could not find the cell containing particle 501
Could not find the cell containing particle 876
Could not find the cell containing particle 251
WARNING: Could not find the cell containing particle 751
WARNING: Could not find the cell containing particle 626
WARNING: Could not find the cell containing particle 376
WARNING: Could not find the cell containing particle 126
Traceback (most recent call last):
File "example_unstructured_mesh_simulation.py", line 99, in
model.run()
File "/home/qxia/.local/lib/python3.8/site-packages/openmc/model/model.py", line 228, in run
openmc.run(**kwargs)
File "/home/qxia/.local/lib/python3.8/site-packages/openmc/executor.py", line 218, in run
_run(args, output, cwd)
File "/home/qxia/.local/lib/python3.8/site-packages/openmc/executor.py", line 28, in _run
raise subprocess.CalledProcessError(p.returncode, ' '.join(args),
subprocess.CalledProcessError: Command 'openmc' died with <Signals.SIGSEGV: 11>.
# creates a source object
source = openmc.Source()
if False:
plasma_params = {
"elongation": 2.9,
"ion_density_origin": 1.09e20,
"ion_density_peaking_factor": 1,
"ion_density_pedestal": 1.09e20,
"ion_density_separatrix": 3e19,
"ion_temperature_origin": 45.9,
"ion_temperature_peaking_factor": 8.06,
"ion_temperature_pedestal": 6.09,
"ion_temperature_separatrix": 0.1,
"major_radius": 1.9*100,
"minor_radius": 1.118*100,
"pedestal_radius": 0.8 * 1.118*100,
"plasma_id": 1,
"shafranov_shift": 0.44789,
"triangularity": 0.270,
"ion_temperature_beta": 6,
}
plasma = PlasmaSource(**plasma_params)
# this creates a neutron distribution with the shape of a tokamak plasma
#source = openmc.Source()
source.library = SOURCE_SAMPLING_PATH
source.parameters = str(plasma)
else:
# point source from task4
source.space = openmc.stats.Point((0, 0, 0))
source.angle = openmc.stats.Isotropic()
source.energy = openmc.stats.Discrete([14e6], [1])
sett.source = source
The text was updated successfully, but these errors were encountered:
Ive no idea on this im afraid, with a volume source its possible that particles are being born on surfaces, which is naughty, but not really a parametric plasma source problem.
here is error message
task12 code
use a plain point source coming with OpenMC official is fine, as suggested by Jonathon. see the code tweak at the end.
===============> FIXED SOURCE TRANSPORT SIMULATION <===============
Simulating batch 1
WARNING: WARNING: WARNING: Could not find the cell containing particle 1
WARNING: Could not find the cell containing particle 501
Could not find the cell containing particle 876
Could not find the cell containing particle 251
WARNING: Could not find the cell containing particle 751
WARNING: Could not find the cell containing particle 626
WARNING: Could not find the cell containing particle 376
WARNING: Could not find the cell containing particle 126
Traceback (most recent call last):
File "example_unstructured_mesh_simulation.py", line 99, in
model.run()
File "/home/qxia/.local/lib/python3.8/site-packages/openmc/model/model.py", line 228, in run
openmc.run(**kwargs)
File "/home/qxia/.local/lib/python3.8/site-packages/openmc/executor.py", line 218, in run
_run(args, output, cwd)
File "/home/qxia/.local/lib/python3.8/site-packages/openmc/executor.py", line 28, in _run
raise subprocess.CalledProcessError(p.returncode, ' '.join(args),
subprocess.CalledProcessError: Command 'openmc' died with <Signals.SIGSEGV: 11>.
The text was updated successfully, but these errors were encountered: