Add 0.13.2 release notes

Author: paulromano

docs/source/io_formats/statepoint.rst

@@ -109,7 +109,8 @@ The current version of the statepoint file format is 17.0.
            - **y** (*double[]*) -- Interpolant values for energyfunction
              interpolation. Only used for 'energyfunction' filters.
 
-             :Attributes: - **interpolation** (*int*) -- Interpolation type. Only used for
+             :Attributes:
+                          - **interpolation** (*int*) -- Interpolation type. Only used for
                             'energyfunction' filters.
 
 **/tallies/derivatives/derivative <id>/**

docs/source/pythonapi/stats.rst

@@ -22,6 +22,12 @@ Univariate Probability Distributions
    openmc.stats.Legendre
    openmc.stats.Mixture
    openmc.stats.Normal
+
+.. autosummary::
+   :toctree: generated
+   :nosignatures:
+   :template: myfunction.rst
+
    openmc.stats.muir
 
 Angular Distributions

docs/source/releasenotes/0.14.0.rst

@@ -0,0 +1,99 @@
+====================
+What's New in 0.14.0
+====================
+
+.. currentmodule:: openmc
+
+-------
+Summary
+-------
+
+This release of OpenMC includes several bug fixes, performance improvements for
+complex geometries and depletion simulations, and other general enhancements.
+Notably, a capability has been added to compute the photon spectra from decay of
+unstable nuclides. Alongside that, a new :data:`openmc.config` configuration
+variable has been introduced that allows easier configuration of data sources.
+Additionally, users can now perform cell or material rejection when sampling
+external source distributions. Finally,
+
+------------------------------------
+Compatibility Notes and Deprecations
+------------------------------------
+
+- If you are building against libMesh for unstructured mesh tally support,
+  version 1.6 or higher is now required.
+- The ``openmc.stats.Muir`` class has been replaced by a
+  :func:`openmc.stats.muir` function that returns an instance of
+  :class:`openmc.stats.Normal`.
+
+------------
+New Features
+------------
+
+- The :meth:`openmc.Material.get_nuclide_atom_densities` method now takes an
+  optional ``nuclide`` argument.
+- Functions/methods in the :mod:`openmc.deplete` module now accept times in
+  Julian years (``'a'``).
+- The :meth:`openmc.Universe.plot` method now allows a pre-existing axes object
+  to be passed in.
+- Performance optimization for geometries with many complex regions.
+- Performance optimization for depletion by avoiding deepcopies and caching
+  reaction rates.
+- The :class:`openmc.RegularMesh` class now has a
+  :meth:`~openmc.RegularMesh.from_domain` classmethod.
+- The :class:`openmc.CylindricalMesh` class now has a
+  :meth:`~openmc.CylindricalMesh.from_domain` classmethod.
+- Improved method to condense diffusion coefficients from the :mod:`openmc.mgxs`
+  module.
+- A new :data:`openmc.config` configuration variable has been introduced that
+  allows data sources to be specified at runtime or via environment variables.
+- The :class:`openmc.EnergyFunctionFilter` class now supports multiple
+  interpolation schemes, not just linear-linear interpolation.
+- The :class:`openmc.DAGMCUniverse` class now has ``material_names``,
+  ``n_cells``, and ``n_surfaces`` attributes.
+- A new :func:`openmc.data.decay_photon_energy` function has been added that
+  returns the energy spectrum of photons emitted from the decay of an unstable
+  nuclide.
+- The :class:`openmc.Material` class also has a new
+  :attr:`~openmc.Material.decay_photon_energy` attribute that gives the decay
+  photon energy spectrum from the material based on its constituent nuclides.
+- The :class:`openmc.deplete.StepResult` now has a
+  :meth:`~openmc.deplete.StepResult.get_material` method.
+- The :class:`openmc.Source` class now takes a ``domains`` argument that
+  specifies a list of cells, materials, or universes that is used to reject
+  source sites (i.e., if the sampled sites are not within the specified domain,
+  they are rejected).
+
+---------
+Bug Fixes
+---------
+
+- `Delay call to Tally::set_strides <https://github.com/openmc-dev/openmc/pull/2183>`
+- `Fix reading reference direction from XML for angular distributions <https://github.com/openmc-dev/openmc/pull/2204>`_
+- `Fix erroneous behavior in Material.add_components <https://github.com/openmc-dev/openmc/pull/2205>`_
+- `Fix reading thermal elastic data from ACE <https://github.com/openmc-dev/openmc/pull/2226>`_
+- `Fix reading source file with time attribute <https://github.com/openmc-dev/openmc/pull/2228>`_
+- `Fix conversion of multiple thermal scattering data files from ACE <https://github.com/openmc-dev/openmc/pull/2232>`_
+- `Fix reading values from wwinp file <https://github.com/openmc-dev/openmc/pull/2242>`_
+- `Handle possibility of .ppm file in Universe.plot <https://github.com/openmc-dev/openmc/pull/2251>`_
+- `Update volume calc types to mitigate overflow issues <https://github.com/openmc-dev/openmc/pull/2270>`_
+
+------------
+Contributors
+------------
+
+- `Lewis Gross <https://github.com/lewisgross1296>`_
+- `Andrew Johnson <https://github.com/drewejohnson>`_
+- `Miriam Kreher <https://github.com/mkreher13>`_
+- `James Logan <https://github.com/jlogan03>`_
+- `Jose Ignacio Marquez Damien <https://github.com/marquezj>`_
+- `Josh May <https://github.com/joshmay1>`_
+- `Patrick Myers <https://github.com/myerspat>`_
+- `Adam Nelson <https://github.com/nelsonag>`_
+- `April Novak <https://github.com/aprilnovak>`_
+- `Ethan Peterson <https://github.com/eepeterson>`_
+- `Gavin Ridley <https://github.com/gridley>`_
+- `Paul Romano <https://github.com/paulromano>`_
+- `Patrick Shriwise <https://github.com/pshriwise>`_
+- `Jonathan Shimwell <https://github.com/Shimwell>`_
+- `Olek Yardas <https://github.com/yardasol>`_

docs/source/releasenotes/index.rst

@@ -7,6 +7,7 @@ Release Notes
 .. toctree::
   :maxdepth: 1
 
+  0.14.0
   0.13.1
   0.13.0
   0.12.2

openmc/material.py

@@ -825,6 +825,8 @@ def get_nuclides(self, element: Optional[str] = None):
         element : str
             Specifies the element to match when searching through the nuclides
 
+            .. versionadded:: 0.14.0
+
         Returns
         -------
         nuclides : list of str
@@ -877,6 +879,8 @@ def get_nuclide_atom_densities(self, nuclide: Optional[str] = None):
             Nuclide for which atom density is desired. If not specified, the
             atom density for each nuclide in the material is given.
 
+            .. versionadded:: 0.14.0
+
         Returns
         -------
         nuclides : dict

openmc/universe.py

@@ -650,19 +650,26 @@ class DAGMCUniverse(UniverseBase):
     bounding_box : 2-tuple of numpy.array
         Lower-left and upper-right coordinates of an axis-aligned bounding box
         of the universe.
+
+        .. versionadded:: 0.13.1
     material_names : list of str
         Return a sorted list of materials names that are contained within the
         DAGMC h5m file. This is useful when naming openmc.Material() objects
         as each material name present in the DAGMC h5m file must have a
         matching openmc.Material() with the same name.
+
+        .. versionadded:: 0.14.0
     n_cells : int
         The number of cells in the DAGMC model. This is the number of cells at
         runtime and accounts for the implicit complement whether or not is it
         present in the DAGMC file.
+
+        .. versionadded:: 0.14.0
     n_surfaces : int
         The number of surfaces in the model.
 
-        .. versionadded:: 0.13.1
+        .. versionadded:: 0.14.0
+
     """
 
     def __init__(self,