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updating for 2 comments per @wbinventory

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This commit is contained in:
Adam Nelson 2016-05-23 21:31:23 -04:00
parent 7aac426860
commit 18447b7f00
2 changed files with 3 additions and 12 deletions
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6
openmc/mgxs/library.py
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@ -460,11 +460,7 @@ class Library(object):
----------
domain : Material or Cell or Universe or Integral
The material, cell, or universe object of interest (or its ID)
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'}
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'}
The type of multi-group cross section object to return
Returns

9
openmc/mgxs/mgxs.py
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@ -427,11 +427,7 @@ class MGXS(object):
Parameters
----------
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'}
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'}
The type of multi-group cross section object to return
domain : openmc.Material or openmc.Cell or openmc.Universe
The domain for spatial homogenization
@ -1810,8 +1806,7 @@ class MatrixMGXS(MGXS):
"""
# Call super class method and null out derived tallies
slice_xs = super(NuFissionMatrixXS, self).get_slice(nuclides,
in_groups)
slice_xs = super(MatrixMGXS, self).get_slice(nuclides, in_groups)
slice_xs._rxn_rate_tally = None
slice_xs._xs_tally = None