OpenMC/docs/source/pythonapi/examples/tallies.xml

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XML

<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10014">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter-P1 nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10013">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10011">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10006">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filter bins="1" type="cell" />
<filter bins="0.0 20.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
</tallies>