OpenMC/tests/test_fixed_source/materials.xml

10 lines
170 B
XML
Raw Permalink Normal View History

<?xml version="1.0"?>
<materials>
<material id="1">
<density value="7.5" units="g/cc" />
<nuclide name="O-16" xs="70c" ao="1.0" />
</material>
</materials>