OpenMC/examples/python/reflective/materials.xml

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XML

<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<!--fuel-->
<material id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U-235" />
</material>
</materials>