OpenMC/tests/test_particle_restart/materials.xml
2013-06-16 16:10:38 -04:00

9 lines
172 B
XML

<?xml version="1.0"?>
<materials>
<material id="1">
<density value="20.0" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
</material>
</materials>