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Additional fix: openmc.mgxs.Library was appending nuclide name to a cross section data set twice when creating the XsData object for the MGXSLibrary class
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1 changed files with 1 additions and 2 deletions
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@ -1265,6 +1265,7 @@ class Library:
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i += 1
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else:
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# import pdb; pdb.set_trace()
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# Create the xsdata object and add it to the mgxs_file
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for i, domain in enumerate(self.domains):
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if self.by_nuclide:
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@ -1277,8 +1278,6 @@ class Library:
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xsdata_name = 'set' + str(i + 1)
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else:
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xsdata_name = xsdata_names[i]
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if nuclide != 'total':
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xsdata_name += '_' + nuclide
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xsdata = self.get_xsdata(domain, xsdata_name,
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nuclide=nuclide, xs_type=xs_type)
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