Bump version to 0.14.0-dev (#2740)

CMakeLists.txt

@@ -3,8 +3,8 @@ project(openmc C CXX)
 
 # Set version numbers
 set(OPENMC_VERSION_MAJOR 0)
-set(OPENMC_VERSION_MINOR 13)
-set(OPENMC_VERSION_RELEASE 4)
+set(OPENMC_VERSION_MINOR 14)
+set(OPENMC_VERSION_RELEASE 0)
 set(OPENMC_VERSION ${OPENMC_VERSION_MAJOR}.${OPENMC_VERSION_MINOR}.${OPENMC_VERSION_RELEASE})
 configure_file(include/openmc/version.h.in "${CMAKE_BINARY_DIR}/include/openmc/version.h" @ONLY)
 

docs/source/conf.py

@@ -69,9 +69,9 @@
 # built documents.
 #
 # The short X.Y version.
-version = "0.13"
+version = "0.14"
 # The full version, including alpha/beta/rc tags.
-release = "0.13.4"
+release = "0.14.0"
 
 # The language for content autogenerated by Sphinx. Refer to documentation
 # for a list of supported languages.

openmc/__init__.py

@@ -39,4 +39,4 @@
 from openmc.model import rectangular_prism, hexagonal_prism, Model
 
 
-__version__ = '0.13.4-dev'
+__version__ = '0.14.0-dev'

openmc/bounding_box.py

@@ -9,7 +9,7 @@
 class BoundingBox:
     """Axis-aligned bounding box.
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------

openmc/cell.py

@@ -562,7 +562,7 @@ def clone(self, clone_materials=True, clone_regions=True,  memo=None):
     def plot(self, *args, **kwargs):
         """Display a slice plot of the cell.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/data/library.py

@@ -15,7 +15,7 @@ class DataLibrary(list):
     cross section data from a single file. The dictionary has keys 'path',
     'type', and 'materials'.
 
-    .. versionchanged:: 0.13.4
+    .. versionchanged:: 0.14.0
         This class now behaves like a list rather than requiring you to access
         the list of libraries through a special attribute.
 

openmc/deplete/abc.py

@@ -554,7 +554,7 @@ class Integrator(ABC):
     transfer_rates : openmc.deplete.TransferRates
         Instance of TransferRates class to perform continuous transfer during depletion
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
     """
 

openmc/deplete/chain.py

@@ -689,7 +689,7 @@ def form_matrix(self, rates, fission_yields=None):
     def form_rr_term(self, tr_rates, mats):
         """Function to form the transfer rate term matrices.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/deplete/coupled_operator.py

@@ -170,7 +170,7 @@ class CoupledOperator(OpenMCOperator):
         equally between the new materials, 'match cell' sets the volume of the
         material to volume of the cell they fill.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
     Attributes
     ----------

openmc/deplete/independent_operator.py

@@ -39,7 +39,7 @@ class IndependentOperator(OpenMCOperator):
 
     .. versionadded:: 0.13.1
 
-    .. versionchanged:: 0.13.4
+    .. versionchanged:: 0.14.0
         Arguments updated to include list of fluxes and microscopic cross
         sections.
 

openmc/deplete/microxs.py

@@ -33,7 +33,7 @@ def get_microxs_and_flux(
     ) -> Tuple[List[np.ndarray], List[MicroXS]]:
     """Generate a microscopic cross sections and flux from a Model
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------
@@ -156,7 +156,7 @@ class MicroXS:
 
     .. versionadded:: 0.13.1
 
-    .. versionchanged:: 0.13.4
+    .. versionchanged:: 0.14.0
         Class was heavily refactored and no longer subclasses pandas.DataFrame.
 
     Parameters

openmc/deplete/openmc_operator.py

@@ -64,7 +64,7 @@ class OpenMCOperator(TransportOperator):
         equally between the new materials, 'match cell' sets the volume of the
         material to volume of the cell they fill.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
     Attributes
     ----------

openmc/deplete/pool.py

@@ -66,7 +66,7 @@ def deplete(func, chain, n, rates, dt, matrix_func=None, transfer_rates=None,
     transfer_rates : openmc.deplete.TransferRates, Optional
         Object to perform continuous reprocessing.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
     matrix_args: Any, optional
         Additional arguments passed to matrix_func
 

openmc/deplete/results.py

@@ -273,7 +273,7 @@ def get_mass(self,
     ) -> Tuple[np.ndarray, np.ndarray]:
         """Get mass of nuclides over time from a single material
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/deplete/stepresult.py

@@ -534,7 +534,7 @@ def save(op, x, op_results, t, source_rate, step_ind, proc_time=None,
         path : PathLike
             Path to file to write. Defaults to 'depletion_results.h5'.
 
-            .. versionadded:: 0.13.4
+            .. versionadded:: 0.14.0
         """
         # Get indexing terms
         vol_dict, nuc_list, burn_list, full_burn_list = op.get_results_info()

openmc/deplete/transfer_rates.py

@@ -16,7 +16,7 @@ class TransferRates:
     An instance of this class can be passed directly to an instance of one of
     the :class:`openmc.deplete.Integrator` classes.
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------

openmc/geometry.py

@@ -738,7 +738,7 @@ def clone(self) -> Geometry:
     def plot(self, *args, **kwargs):
         """Display a slice plot of the geometry.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/lib/core.py

@@ -174,7 +174,7 @@ def export_properties(filename=None, output=True):
 def export_weight_windows(filename="weight_windows.h5", output=True):
     """Export weight windows.
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------
@@ -198,7 +198,7 @@ def export_weight_windows(filename="weight_windows.h5", output=True):
 def import_weight_windows(filename='weight_windows.h5', output=True):
     """Import weight windows.
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------

openmc/lib/tally.py

@@ -183,7 +183,7 @@ class Tally(_FortranObjectWithID):
     multiply_density : bool
         Whether reaction rates should be multiplied by atom density
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
     nuclides : list of str
         List of nuclides to score results for
     num_realizations : int

openmc/lib/weight_windows.py

@@ -109,7 +109,7 @@ class WeightWindows(_FortranObjectWithID):
     OpenMC library. To obtain a view of a weight windows object with a given ID,
     use the :data:`openmc.lib.weight_windows` mapping.
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------
@@ -392,4 +392,4 @@ def __repr__(self):
     def __delitem__(self):
         raise NotImplementedError("WeightWindows object remove not implemented")
 
-weight_windows = _WeightWindowsMapping()
+weight_windows = _WeightWindowsMapping()

openmc/material.py

@@ -289,7 +289,7 @@ def get_decay_photon_energy(
         ) -> Optional[Univariate]:
         r"""Return energy distribution of decay photons from unstable nuclides.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/mesh.py

@@ -1521,7 +1521,7 @@ def volumes(self):
 
     @property
     def vertices(self):
-        warnings.warn('Cartesian coordinates are returned from this property as of version 0.13.4')
+        warnings.warn('Cartesian coordinates are returned from this property as of version 0.14.0')
         return self._convert_to_cartesian(self.vertices_cylindrical, self.origin)
 
     @property
@@ -1532,7 +1532,7 @@ def vertices_cylindrical(self):
 
     @property
     def centroids(self):
-        warnings.warn('Cartesian coordinates are returned from this property as of version 0.13.4')
+        warnings.warn('Cartesian coordinates are returned from this property as of version 0.14.0')
         return self._convert_to_cartesian(self.centroids_cylindrical, self.origin)
 
     @property
@@ -1816,7 +1816,7 @@ def volumes(self):
 
     @property
     def vertices(self):
-        warnings.warn('Cartesian coordinates are returned from this property as of version 0.13.4')
+        warnings.warn('Cartesian coordinates are returned from this property as of version 0.14.0')
         return self._convert_to_cartesian(self.vertices_spherical, self.origin)
 
     @property
@@ -1827,7 +1827,7 @@ def vertices_spherical(self):
 
     @property
     def centroids(self):
-        warnings.warn('Cartesian coordinates are returned from this property as of version 0.13.4')
+        warnings.warn('Cartesian coordinates are returned from this property as of version 0.14.0')
         return self._convert_to_cartesian(self.centroids_spherical, self.origin)
 
     @property

openmc/mgxs/groups.py

@@ -17,7 +17,7 @@ class EnergyGroups:
         The energy group boundaries in [eV] or the name of the group structure
         (Must be a valid key in the openmc.mgxs.GROUP_STRUCTURES dictionary).
 
-        .. versionchanged:: 0.13.4
+        .. versionchanged:: 0.14.0
             Changed to allow a string specifying the group structure name.
 
     Attributes

openmc/model/model.py

@@ -1019,7 +1019,7 @@ def update_material_volumes(self, names_or_ids, volume):
     def differentiate_depletable_mats(self, diff_volume_method: str):
         """Assign distribmats for each depletable material
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/model/surface_composite.py

@@ -1232,7 +1232,7 @@ class CruciformPrism(CompositeSurface):
     multiple distances from the center. Equivalent to the 'gcross' derived
     surface in Serpent.
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------

openmc/plots.py

@@ -184,7 +184,7 @@ def _get_plot_image(plot, cwd):
 def voxel_to_vtk(voxel_file: PathLike, output: PathLike = 'plot.vti'):
     """Converts a voxel HDF5 file to a VTK file
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------
@@ -943,7 +943,7 @@ def to_vtk(self, output: Optional[PathLike] = None,
 
         This method runs OpenMC in plotting mode to produce a .vti file.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/settings.py

@@ -124,7 +124,7 @@ class Settings:
         Maximum number of particle restart files (per MPI process) to write for
         lost particles.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
     no_reduce : bool
         Indicate that all user-defined and global tallies should not be reduced
         across processes in a parallel calculation.
@@ -240,11 +240,11 @@ class Settings:
         Indicates the checkpoints for weight window split/roulettes. Valid keys
         include "collision" and "surface". Values must be of type bool.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
     weight_window_generators : WeightWindowGenerator or iterable of WeightWindowGenerator
         Weight windows generation parameters to apply during simulation
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
     create_delayed_neutrons : bool
         Whether delayed neutrons are created in fission.
@@ -258,7 +258,7 @@ class Settings:
     weight_windows_file: Pathlike
         Path to a weight window file to load during simulation initialization
 
-        .. versionadded::0.13.4
+        .. versionadded::0.14.0
     write_initial_source : bool
         Indicate whether to write the initial source distribution to file
     """

openmc/source.py

@@ -154,7 +154,7 @@ class IndependentSource(SourceBase):
     type : str
         Indicator of source type: 'independent'
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     particle : {'neutron', 'photon'}
         Source particle type
@@ -392,7 +392,7 @@ def Source(*args, **kwargs):
 class CompiledSource(SourceBase):
     """A source based on a compiled shared library
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------
@@ -500,7 +500,7 @@ def from_xml_element(cls, elem: ET.Element, meshes=None) -> openmc.CompiledSourc
 class FileSource(SourceBase):
     """A source based on particles stored in a file
 
-    .. versionadded:: 0.13.4
+    .. versionadded:: 0.14.0
 
     Parameters
     ----------

openmc/stats/univariate.py

@@ -266,7 +266,7 @@ def clip(self, tolerance: float = 1e-6, inplace: bool = False) -> Discrete:
         function will remove any low-importance points such that :math:`\sum_i
         x_i p_i` is preserved to within some threshold.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------
@@ -1281,7 +1281,7 @@ def clip(self, tolerance: float = 1e-6, inplace: bool = False) -> Mixture:
         function will remove any low-importance points such that :math:`\sum_i
         x_i p_i` is preserved to within some threshold.
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
 
         Parameters
         ----------

openmc/tallies.py

@@ -57,7 +57,7 @@ class Tally(IDManagerMixin):
     multiply_density : bool
         Whether reaction rates should be multiplied by atom density
 
-        .. versionadded:: 0.13.4
+        .. versionadded:: 0.14.0
     filters : list of openmc.Filter
         List of specified filters for the tally
     nuclides : list of str