Change 0.14.0 --> 0.13.2

Author: paulromano

CMakeLists.txt

@@ -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)
 

docs/source/conf.py

@@ -69,9 +69,9 @@
 # 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.

docs/source/releasenotes/0.14.0.rst renamed to docs/source/releasenotes/0.13.2.rst

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

docs/source/releasenotes/index.rst

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

openmc/__init__.py

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

openmc/data/decay.py

@@ -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
     ----------

openmc/deplete/stepresult.py

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

openmc/material.py

@@ -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 @@ def get_nuclides(self, element: Optional[str] = None):
         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 @@ 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
+            .. versionadded:: 0.13.2
 
         Returns
         -------

openmc/stats/univariate.py

@@ -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
     ----------

openmc/universe.py

@@ -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
 
     """