OpenMC/tests/test_survival_biasing/materials.xml

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219 B
XML

<?xml version="1.0"?>
<materials>
<material id="1">
<density value="19.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="2.0" />
<nuclide name="U-238" xs="70c" ao="1.0" />
</material>
</materials>