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Add MGMC loading of regular transport cross sections

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guillaume 2019-12-16 17:38:29 -05:00
parent d9195b93f8
commit a50a342f27
1 changed files with 6 additions and 1 deletions
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7
openmc/mgxs/library.py
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@ -999,6 +999,11 @@ class Library(object):
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide],
subdomain=subdomain)
elif 'transport' in self.mgxs_types and self.correction == 'P0':
mymgxs = self.get_mgxs(domain, 'transport')
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide],
subdomain=subdomain)
elif 'total' in self.mgxs_types:
mymgxs = self.get_mgxs(domain, 'total')
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide],
@ -1170,7 +1175,7 @@ class Library(object):
# if only scatter matrices have been tallied, multiplicity cannot
# be accounted for
else:
msg = 'Scatter multiplicity (such as (n,xn) reactions) ' \
msg = 'Scatter multiplicity (such as (n,xn) reactions) '\
'are ignored since multiplicity or nu-scatter matrices '\
'were not tallied for ' + xsdata_name
warn(msg, RuntimeWarning)