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Fixed issues with MultiGroupXS extraction summed across nuclides
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b979a19f73
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1 changed files with 4 additions and 3 deletions
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@ -511,7 +511,7 @@ class MultiGroupXS(object):
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# NOTE: We must not override the "nuclides" parameter since it is used
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# to retrieve atomic number densities for micro xs
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if self.by_nuclide:
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if nuclides == 'all' or nuclides == 'sum':
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if nuclides == 'all' or nuclides == 'sum' or nuclides == ['sum']:
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query_nuclides = self.get_all_nuclides()
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else:
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query_nuclides = nuclides
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@ -1513,7 +1513,7 @@ class ScatterMatrixXS(MultiGroupXS):
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# NOTE: We must not override the "nuclides" parameter since it is used
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# to retrieve atomic number densities for micro xs
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if self.by_nuclide:
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if nuclides == 'all' or nuclides == 'sum':
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if nuclides == 'all' or nuclides == 'sum' or nuclides == ['sum']:
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query_nuclides = self.get_all_nuclides()
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else:
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query_nuclides = nuclides
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@ -1813,7 +1813,7 @@ class Chi(MultiGroupXS):
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# Get the sum as the fission source weighted average chi for all
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# nuclides in the domain
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if nuclides == 'sum':
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if nuclides == 'sum' or nuclides == ['sum']:
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# Retrieve the fission production tallies
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nu_fission_in = self.tallies['nu-fission-in']
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@ -1850,6 +1850,7 @@ class Chi(MultiGroupXS):
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# Reverse data if user requested increasing energy groups since
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# tally data is stored in order of increasing energies
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if order_groups == 'increasing':
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# Reshape tally data array with separate axes for domain and energy
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if groups == 'all':
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num_groups = self.num_groups
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