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Respond to @wbinventor comments on #632
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15 changed files with 146 additions and 138 deletions
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@ -23,7 +23,7 @@ fuel = openmc.Material(material_id=1, name='fuel')
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fuel.set_density('g/cc', 4.5)
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fuel.add_nuclide(u235, 1.)
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# Instantiate a Materials object, register Material, and export to XML
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# Instantiate a Materials collection, register Material, and export to XML
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materials_file = openmc.Materials()
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materials_file.default_xs = '71c'
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materials_file.add_material(fuel)
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@ -64,7 +64,7 @@ root = openmc.Universe(universe_id=0, name='root universe')
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# Register Cell with Universe
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root.add_cell(cell)
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# Instantiate a Geometry and register the root Universe, and export to XML
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# Instantiate a Geometry, register the root Universe, and export to XML
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geometry = openmc.Geometry()
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geometry.root_universe = root
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geometry.export_to_xml()
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