OpenMC/docs/source/pythonapi/examples/materials.xml

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XML

<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<material id="10000" name="moderator">
<density units="g/cc" value="5.0" />
<nuclide ao="0.006886019" name="U-238" />
<nuclide ao="0.01450188" name="O-16" />
<nuclide ao="0.002116053" name="Zr-90" />
<nuclide ao="0.028999667" name="H-1" />
<nuclide ao="0.000114142" name="U-235" />
</material>
</materials>