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Merge pull request #2269 from paulromano/release-0.13.2
Release of version 0.13.2
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‎CMakeLists.txt‎

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# Set version numbers
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set(OPENMC_VERSION_MAJOR 0)
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set(OPENMC_VERSION_MINOR 14)
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set(OPENMC_VERSION_RELEASE 0)
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set(OPENMC_VERSION_MINOR 13)
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set(OPENMC_VERSION_RELEASE 2)
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set(OPENMC_VERSION ${OPENMC_VERSION_MAJOR}.${OPENMC_VERSION_MINOR}.${OPENMC_VERSION_RELEASE})
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configure_file(include/openmc/version.h.in "${CMAKE_BINARY_DIR}/include/openmc/version.h" @ONLY)
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‎docs/source/conf.py‎

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# built documents.
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#
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# The short X.Y version.
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version = "0.14"
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version = "0.13"
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# The full version, including alpha/beta/rc tags.
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release = "0.14.0"
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release = "0.13.2"
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# The language for content autogenerated by Sphinx. Refer to documentation
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# for a list of supported languages.

‎docs/source/io_formats/statepoint.rst‎

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- **y** (*double[]*) -- Interpolant values for energyfunction
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interpolation. Only used for 'energyfunction' filters.
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:Attributes: - **interpolation** (*int*) -- Interpolation type. Only used for
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:Attributes:
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- **interpolation** (*int*) -- Interpolation type. Only used for
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'energyfunction' filters.
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**/tallies/derivatives/derivative <id>/**

‎docs/source/pythonapi/stats.rst‎

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openmc.stats.Legendre
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openmc.stats.Mixture
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openmc.stats.Normal
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myfunction.rst
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openmc.stats.muir
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Angular Distributions

‎docs/source/releasenotes/0.13.2.rst‎

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====================
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What's New in 0.13.2
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====================
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.. currentmodule:: openmc
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-------
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Summary
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-------
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This release of OpenMC includes several bug fixes, performance improvements for
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complex geometries and depletion simulations, and other general enhancements.
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Notably, a capability has been added to compute the photon spectra from decay of
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unstable nuclides. Alongside that, a new :data:`openmc.config` configuration
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variable has been introduced that allows easier configuration of data sources.
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Additionally, users can now perform cell or material rejection when sampling
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external source distributions. Finally,
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------------------------------------
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Compatibility Notes and Deprecations
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------------------------------------
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- If you are building against libMesh for unstructured mesh tally support,
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version 1.6 or higher is now required.
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- The ``openmc.stats.Muir`` class has been replaced by a
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:func:`openmc.stats.muir` function that returns an instance of
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:class:`openmc.stats.Normal`.
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------------
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New Features
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------------
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- The :meth:`openmc.Material.get_nuclide_atom_densities` method now takes an
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optional ``nuclide`` argument.
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- Functions/methods in the :mod:`openmc.deplete` module now accept times in
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Julian years (``'a'``).
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- The :meth:`openmc.Universe.plot` method now allows a pre-existing axes object
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to be passed in.
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- Performance optimization for geometries with many complex regions.
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- Performance optimization for depletion by avoiding deepcopies and caching
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reaction rates.
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- The :class:`openmc.RegularMesh` class now has a
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:meth:`~openmc.RegularMesh.from_domain` classmethod.
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- The :class:`openmc.CylindricalMesh` class now has a
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:meth:`~openmc.CylindricalMesh.from_domain` classmethod.
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- Improved method to condense diffusion coefficients from the :mod:`openmc.mgxs`
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module.
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- A new :data:`openmc.config` configuration variable has been introduced that
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allows data sources to be specified at runtime or via environment variables.
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- The :class:`openmc.EnergyFunctionFilter` class now supports multiple
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interpolation schemes, not just linear-linear interpolation.
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- The :class:`openmc.DAGMCUniverse` class now has ``material_names``,
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``n_cells``, and ``n_surfaces`` attributes.
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- A new :func:`openmc.data.decay_photon_energy` function has been added that
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returns the energy spectrum of photons emitted from the decay of an unstable
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nuclide.
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- The :class:`openmc.Material` class also has a new
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:attr:`~openmc.Material.decay_photon_energy` attribute that gives the decay
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photon energy spectrum from the material based on its constituent nuclides.
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- The :class:`openmc.deplete.StepResult` now has a
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:meth:`~openmc.deplete.StepResult.get_material` method.
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- The :class:`openmc.Source` class now takes a ``domains`` argument that
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specifies a list of cells, materials, or universes that is used to reject
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source sites (i.e., if the sampled sites are not within the specified domain,
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they are rejected).
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---------
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Bug Fixes
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---------
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- `Delay call to Tally::set_strides <https://github.com/openmc-dev/openmc/pull/2183>`_
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- `Fix reading reference direction from XML for angular distributions <https://github.com/openmc-dev/openmc/pull/2204>`_
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- `Fix erroneous behavior in Material.add_components <https://github.com/openmc-dev/openmc/pull/2205>`_
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- `Fix reading thermal elastic data from ACE <https://github.com/openmc-dev/openmc/pull/2226>`_
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- `Fix reading source file with time attribute <https://github.com/openmc-dev/openmc/pull/2228>`_
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- `Fix conversion of multiple thermal scattering data files from ACE <https://github.com/openmc-dev/openmc/pull/2232>`_
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- `Fix reading values from wwinp file <https://github.com/openmc-dev/openmc/pull/2242>`_
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- `Handle possibility of .ppm file in Universe.plot <https://github.com/openmc-dev/openmc/pull/2251>`_
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- `Update volume calc types to mitigate overflow issues <https://github.com/openmc-dev/openmc/pull/2270>`_
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------------
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Contributors
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------------
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- `Lewis Gross <https://github.com/lewisgross1296>`_
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- `Andrew Johnson <https://github.com/drewejohnson>`_
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- `Miriam Kreher <https://github.com/mkreher13>`_
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- `James Logan <https://github.com/jlogan03>`_
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- `Jose Ignacio Marquez Damien <https://github.com/marquezj>`_
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- `Josh May <https://github.com/joshmay1>`_
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- `Patrick Myers <https://github.com/myerspat>`_
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- `Adam Nelson <https://github.com/nelsonag>`_
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- `April Novak <https://github.com/aprilnovak>`_
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- `Ethan Peterson <https://github.com/eepeterson>`_
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- `Gavin Ridley <https://github.com/gridley>`_
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- `Paul Romano <https://github.com/paulromano>`_
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- `Patrick Shriwise <https://github.com/pshriwise>`_
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- `Jonathan Shimwell <https://github.com/Shimwell>`_
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- `Olek Yardas <https://github.com/yardasol>`_

‎docs/source/releasenotes/index.rst‎

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.. toctree::
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:maxdepth: 1
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0.13.2
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0.13.1
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0.13.0
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0.12.2

‎include/openmc/constants.h‎

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enum class GeometryType { CSG, DAG };
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//==============================================================================
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// Volume Calculation Constants
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constexpr uint64_t UINT64_T_MAX {std::numeric_limits<uint64_t>::max()};
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} // namespace openmc
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#endif // OPENMC_CONSTANTS_H

‎include/openmc/version.h.in‎

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constexpr int VERSION_MAJOR {@OPENMC_VERSION_MAJOR@};
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constexpr int VERSION_MINOR {@OPENMC_VERSION_MINOR@};
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constexpr int VERSION_RELEASE {@OPENMC_VERSION_RELEASE@};
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constexpr bool VERSION_DEV {true};
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constexpr bool VERSION_DEV {false};
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constexpr std::array<int, 3> VERSION {VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE};
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// clang-format on
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‎openmc/__init__.py‎

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from openmc.model import rectangular_prism, hexagonal_prism, Model
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__version__ = '0.14.0-dev'
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__version__ = '0.13.2'

‎openmc/data/decay.py‎

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for the first time, you need to ensure that a depletion chain has been
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specified in openmc.config['chain_file'].
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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Parameters
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----------

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