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Major refactor to include cross sections at multiple temperatures within the
Nuclide and SAlphaData derived types.
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121 changed files with 1670 additions and 2213 deletions
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@ -37,7 +37,6 @@ iron.add_nuclide(fe56, 1.)
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([moderator, fuel, iron])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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