Change 0.14.0 --> 0.13.2

This commit is contained in:
Paul Romano 2022-10-19 08:04:50 -05:00
parent a0e5ba4418
commit 53b6d8ab11
10 changed files with 16 additions and 16 deletions

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@ -3,8 +3,8 @@ project(openmc C CXX)
# Set version numbers
set(OPENMC_VERSION_MAJOR 0)
set(OPENMC_VERSION_MINOR 14)
set(OPENMC_VERSION_RELEASE 0)
set(OPENMC_VERSION_MINOR 13)
set(OPENMC_VERSION_RELEASE 2)
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)

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@ -69,9 +69,9 @@ copyright = '2011-2022, Massachusetts Institute of Technology, UChicago Argonne
# built documents.
#
# The short X.Y version.
version = "0.14"
version = "0.13"
# The full version, including alpha/beta/rc tags.
release = "0.14.0"
release = "0.13.2"
# The language for content autogenerated by Sphinx. Refer to documentation
# for a list of supported languages.

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@ -1,5 +1,5 @@
====================
What's New in 0.14.0
What's New in 0.13.2
====================
.. currentmodule:: openmc

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@ -7,7 +7,7 @@ Release Notes
.. toctree::
:maxdepth: 1
0.14.0
0.13.2
0.13.1
0.13.0
0.12.2

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@ -38,4 +38,4 @@ from .config import *
from openmc.model import rectangular_prism, hexagonal_prism, Model
__version__ = '0.14.0-dev'
__version__ = '0.13.2-dev'

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@ -587,7 +587,7 @@ def decay_photon_energy(nuclide: str) -> Optional[Univariate]:
for the first time, you need to ensure that a depletion chain has been
specified in openmc.config['chain_file'].
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
Parameters
----------

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@ -202,7 +202,7 @@ class StepResult:
def get_material(self, mat_id):
"""Return material object for given depleted composition
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
Parameters
----------

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@ -98,7 +98,7 @@ class Material(IDManagerMixin):
this distribution is the total intensity of the photon source in
[decay/sec].
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
"""
@ -825,7 +825,7 @@ class Material(IDManagerMixin):
element : str
Specifies the element to match when searching through the nuclides
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
Returns
-------
@ -879,7 +879,7 @@ class Material(IDManagerMixin):
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
.. versionadded:: 0.13.2
Returns
-------

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@ -729,7 +729,7 @@ def muir(e0, m_rat, kt):
distribution: the mean energy of particles ``e0``, the mass of reactants
``m_rat``, and the ion temperature ``kt``.
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
Parameters
----------

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@ -658,17 +658,17 @@ class DAGMCUniverse(UniverseBase):
as each material name present in the DAGMC h5m file must have a
matching openmc.Material() with the same name.
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
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
.. versionadded:: 0.13.2
n_surfaces : int
The number of surfaces in the model.
.. versionadded:: 0.14.0
.. versionadded:: 0.13.2
"""