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Change 0.14.0 --> 0.13.2
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10 changed files with 16 additions and 16 deletions
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@ -3,8 +3,8 @@ project(openmc C CXX)
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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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@ -69,9 +69,9 @@ copyright = '2011-2022, Massachusetts Institute of Technology, UChicago Argonne
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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.
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@ -1,5 +1,5 @@
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====================
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What's New in 0.14.0
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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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@ -7,7 +7,7 @@ Release Notes
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.. toctree::
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:maxdepth: 1
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0.14.0
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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
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@ -38,4 +38,4 @@ from .config import *
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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-dev'
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@ -587,7 +587,7 @@ def decay_photon_energy(nuclide: str) -> Optional[Univariate]:
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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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@ -202,7 +202,7 @@ class StepResult:
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def get_material(self, mat_id):
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"""Return material object for given depleted composition
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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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@ -98,7 +98,7 @@ class Material(IDManagerMixin):
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this distribution is the total intensity of the photon source in
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[decay/sec].
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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"""
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@ -825,7 +825,7 @@ class Material(IDManagerMixin):
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element : str
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Specifies the element to match when searching through the nuclides
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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Returns
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-------
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@ -879,7 +879,7 @@ class Material(IDManagerMixin):
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Nuclide for which atom density is desired. If not specified, the
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atom density for each nuclide in the material is given.
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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Returns
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-------
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@ -729,7 +729,7 @@ def muir(e0, m_rat, kt):
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distribution: the mean energy of particles ``e0``, the mass of reactants
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``m_rat``, and the ion temperature ``kt``.
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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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@ -658,17 +658,17 @@ class DAGMCUniverse(UniverseBase):
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as each material name present in the DAGMC h5m file must have a
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matching openmc.Material() with the same name.
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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n_cells : int
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The number of cells in the DAGMC model. This is the number of cells at
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runtime and accounts for the implicit complement whether or not is it
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present in the DAGMC file.
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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n_surfaces : int
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The number of surfaces in the model.
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.. versionadded:: 0.14.0
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.. versionadded:: 0.13.2
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"""
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