OpenMC/examples/pincell/materials.xml
2013-03-23 10:43:16 -04:00

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XML

<?xml version="1.0"?>
<materials>
<!-- By default, use 600K cross sections -->
<default_xs>71c</default_xs>
<!--
Since O-18 is not present in ENDF/B-VII, it was necessary to combine the
atom densities for O-17 and O-18 in any materials containing Oxygen.
-->
<!-- UO2 fuel at 2.4 wt% enrichment -->
<material id="1">
<density value="10.29769" units="g/cm3" />
<nuclide name="U-234" ao="4.4843e-06" />
<nuclide name="U-235" ao="5.5815e-04" />
<nuclide name="U-238" ao="2.2408e-02" />
<nuclide name="O-16" ao="4.5829e-02" />
<nuclide name="O-17" ao="1.1164e-04" />
</material>
<!-- Helium for gap -->
<material id="2">
<density value="0.001598" units="g/cm3" />
<nuclide name="He-4" ao="2.4044e-04" />
</material>
<!-- Zircaloy 4 -->
<material id="3">
<density value="6.55" units="g/cm3" />
<nuclide name="O-16" ao="3.0743e-04" />
<nuclide name="O-17" ao="7.4887e-07" />
<nuclide name="Cr-50" ao="3.2962e-06" />
<nuclide name="Cr-52" ao="6.3564e-05" />
<nuclide name="Cr-53" ao="7.2076e-06" />
<nuclide name="Cr-54" ao="1.7941e-06" />
<nuclide name="Fe-54" ao="8.6699e-06" />
<nuclide name="Fe-56" ao="1.3610e-04" />
<nuclide name="Fe-57" ao="3.1431e-06" />
<nuclide name="Fe-58" ao="4.1829e-07" />
<nuclide name="Zr-90" ao="2.1827e-02" />
<nuclide name="Zr-91" ao="4.7600e-03" />
<nuclide name="Zr-92" ao="7.2758e-03" />
<nuclide name="Zr-94" ao="7.3734e-03" />
<nuclide name="Zr-96" ao="1.1879e-03" />
<nuclide name="Sn-112" ao="4.6735e-06" />
<nuclide name="Sn-114" ao="3.1799e-06" />
<nuclide name="Sn-115" ao="1.6381e-06" />
<nuclide name="Sn-116" ao="7.0055e-05" />
<nuclide name="Sn-117" ao="3.7003e-05" />
<nuclide name="Sn-118" ao="1.1669e-04" />
<nuclide name="Sn-119" ao="4.1387e-05" />
<nuclide name="Sn-120" ao="1.5697e-04" />
<nuclide name="Sn-122" ao="2.2308e-05" />
<nuclide name="Sn-124" ao="2.7897e-05" />
</material>
<!-- Borated water at 975 ppm -->
<material id="4">
<density value="0.740582" units="g/cm3" />
<nuclide name="B-10" ao="8.0042e-06" />
<nuclide name="B-11" ao="3.2218e-05" />
<nuclide name="H-1" ao="4.9457e-02" />
<nuclide name="H-2" ao="7.4196e-06" />
<nuclide name="O-16" ao="2.4672e-02" />
<nuclide name="O-17" ao="6.0099e-05" />
<sab name="lwtr" xs="15t" />
</material>
</materials>