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Sam Shaner 2016-07-31 10:20:50 -04:00
parent 10795fd00f
commit 355fb6f30d
3 changed files with 8 additions and 7 deletions
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4
docs/source/pythonapi/examples/mgxs-part-iv.ipynb
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@ -519,9 +519,9 @@
"cell_type": "markdown",
"metadata": {},
"source": [
"Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material\" \"cell\", \"universe\", and \"mesh\" domain types. In this simple example, we wish to compute multi-group cross sections only for each material andtherefore will use a \"material\" domain type.\n",
"Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material\" \"cell\", \"universe\", and \"mesh\" domain types. In this simple example, we wish to compute multi-group cross sections only for each material and therefore will use a \"material\" domain type.\n",
"\n",
"**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell, universe, or mesh cell) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property."
"**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell, universe, or mesh) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property."
]
},
{

3
openmc/mgxs/library.py
View file

@ -56,8 +56,7 @@ class Library(object):
The types of cross sections in the library (e.g., ['total', 'scatter'])
domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'}
Domain type for spatial homogenization
domains : Iterable of openmc.Material, openmc.Cell, openmc.Universe or
openmc.Mesh
domains : Iterable of openmc.Material, openmc.Cell, openmc.Universe or openmc.Mesh
The spatial domain(s) for which MGXS in the Library are computed
correction : {'P0', None}
Apply the P0 correction to scattering matrices if set to 'P0'

8
openmc/mgxs/mgxs.py
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@ -439,8 +439,7 @@ class MGXS(object):
----------
mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'multiplicity matrix', 'nu-fission matrix', 'chi', 'chi-prompt', 'inverse-velocity', 'prompt-nu-fission'}
The type of multi-group cross section object to return
domain : openmc.Material or openmc.Cell or openmc.Universe or
openmc.Mesh
domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.Mesh
The domain for spatial homogenization
domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'}
The domain type for spatial homogenization
@ -1491,7 +1490,10 @@ class MGXS(object):
distribcell_paths=distribcell_paths)
# Remove nuclide column since it is homogeneous and redundant
df.drop('nuclide', axis=1, inplace=True)
if self.domain_type == 'mesh':
df.drop('nuclide', axis=1, level=0, inplace=True)
else:
df.drop('nuclide', axis=1, inplace=True)
# If the user requested a specific set of nuclides
elif self.by_nuclide and nuclides != 'all':