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added enrichment and wo element support in Python API and added new tests
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12 changed files with 278 additions and 46 deletions
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@ -45,18 +45,14 @@ sn119 = openmc.Nuclide('Sn119')
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sn120 = openmc.Nuclide('Sn120')
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sn122 = openmc.Nuclide('Sn122')
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sn124 = openmc.Nuclide('Sn124')
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u234 = openmc.Nuclide('U234')
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u235 = openmc.Nuclide('U235')
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u238 = openmc.Nuclide('U238')
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u = openmc.Element('U')
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o = openmc.Element('O')
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# Instantiate some Materials and register the appropriate Nuclides
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uo2 = openmc.Material(material_id=1, name='UO2 fuel at 2.4% wt enrichment')
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uo2.set_density('g/cm3', 10.29769)
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uo2.add_nuclide(u234, 4.4843e-6)
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uo2.add_nuclide(u235, 5.5815e-4)
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uo2.add_nuclide(u238, 2.2408e-2)
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uo2.add_nuclide(o16, 4.5829e-2)
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uo2.add_nuclide(o17, 1.1164e-4)
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uo2.add_element(u, 1., enrichment=0.05)
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uo2.add_element(o, 2.)
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helium = openmc.Material(material_id=2, name='Helium for gap')
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helium.set_density('g/cm3', 0.001598)
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