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Address @nelsonag 's review

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guillaume 2019-12-16 17:35:19 -05:00
parent 80dc996717
commit d9195b93f8
1 changed files with 5 additions and 5 deletions
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10
openmc/mgxs/library.py
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@ -1172,7 +1172,7 @@ class Library(object):
else:
msg = 'Scatter multiplicity (such as (n,xn) reactions) ' \
'are ignored since multiplicity or nu-scatter matrices '\
'were not tallied for '+xsdata_name
'were not tallied for ' + xsdata_name
warn(msg, RuntimeWarning)
xsdata.set_scatter_matrix_mgxs(scatt_mgxs, xs_type=xs_type,
nuclide=[nuclide],
@ -1420,8 +1420,9 @@ class Library(object):
fixed source problem could be the target.
- Fission and kappa-fission are not required as they are only
needed to support tallies the user may wish to request.
- Scattering multiplicity should have been tallied, either using a
multiplicity or scatter and nu-scatter matrix tally.
- Scattering multiplicity should have been tallied for increased model
accuracy, either using a multiplicity or scatter and nu-scatter matrix
tally.
See also
--------
@ -1478,9 +1479,8 @@ class Library(object):
'nu-scatter matrix' not in self.mgxs_types) and\
('consistent scatter matrix' not in self.mgxs_types or
'consistent nu-scatter matrix' not in self.mgxs_types):
error_flag = True
warn('A "multiplicity matrix" or both a "scatter" and "nu-scatter" '
'matrix MGXS type(s) is/are required.')
'matrix MGXS type(s) should be provided.')
# Ensure absorption is present
if 'absorption' not in self.mgxs_types: