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Merge pull request #619 from wbinventor/fix-mgxs-nuclides

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Hotfix for User-Specified Nuclides to MGXS
This commit is contained in:
Paul Romano 2016-03-28 22:16:34 -05:00
commit 669bc206e2
1 changed files with 7 additions and 9 deletions
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16
openmc/mgxs/mgxs.py
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@ -67,10 +67,6 @@ class MGXS(object):
The energy group structure for energy condensation
by_nuclide : bool
If true, computes cross sections for each nuclide in domain
nuclides : Iterable of basestring
The user-specified nuclides to compute cross sections. If by_nuclide
is True but nuclides are not specified by the user, all nuclides in the
spatial domain will be used.
name : str, optional
Name of the multi-group cross section. Used as a label to identify
tallies in OpenMC 'tallies.xml' file.
@ -109,9 +105,11 @@ class MGXS(object):
num_nuclides : Integral
The number of nuclides for which the multi-group cross section is
being tracked. This is unity if the by_nuclide attribute is False.
nuclides : list of str or 'sum'
A list of nuclide string names (e.g., 'U-238', 'O-16') when by_nuclide
is True and 'sum' when by_nuclide is False.
nuclides : Iterable of str or 'sum'
The optional user-specified nuclides for which to compute cross
sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides
are not specified by the user, all nuclides in the spatial domain
are included. This attribute is 'sum' if by_nuclide is false.
sparse : bool
Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format
for compressed data storage
@ -441,7 +439,7 @@ class MGXS(object):
cv.check_type('nuclide', nuclide, basestring)
# Get list of all nuclides in the spatial domain
nuclides = self.domain.get_all_nuclides()
nuclides = self.get_all_nuclides()
if nuclide not in nuclides:
msg = 'Unable to get density for nuclide "{0}" which is not in ' \
@ -553,7 +551,7 @@ class MGXS(object):
# If this is a by-nuclide cross-section, add all nuclides to Tally
if self.by_nuclide and score != 'flux':
all_nuclides = self.domain.get_all_nuclides()
all_nuclides = self.get_all_nuclides()
for nuclide in all_nuclides:
self.tallies[key].nuclides.append(nuclide)
else: