OpenMC/tests/test_sourcepoint_restart/tallies.xml
2014-01-06 10:37:50 -05:00

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XML

<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>rectangular</type>
<dimension>5 3 4</dimension>
<lower_left>-10. -5. 0.</lower_left>
<upper_right>10. 4. 9.</upper_right>
</mesh>
<tally id="10">
<filter type="mesh" bins="1" />
<filter type="energy" bins="0.0 5.0 10.0" />
<filter type="energyout" bins="0.0 5.0 10.0" />
<scores>scatter-P3 nu-fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<scores>fission absorption total flux</scores>
</tally>
</tallies>