OpenMC/tests/regression_tests/photon_production/inputs_true.dat

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1">
<density value="2.6989" units="g/cm3"/>
<nuclide name="Al27" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" material="void" region="-1 2 -3" universe="1"/>
<cell id="2" material="1" region="-1 3 -4" universe="1"/>
<cell id="3" material="void" region="1 | -2 | 4" universe="1"/>
<surface id="1" type="x-cylinder" boundary="vacuum" coeffs="0.0 0.0 1.0"/>
<surface id="2" type="x-plane" boundary="vacuum" coeffs="-1.0"/>
<surface id="3" type="x-plane" coeffs="1.0"/>
<surface id="4" type="x-plane" boundary="vacuum" coeffs="1000000000.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>10000</particles>
<batches>1</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="point">
<parameters>0 0 0</parameters>
</space>
<angle type="monodirectional" reference_uvw="1.0 0.0 0.0"/>
<energy type="discrete">
<parameters>14000000.0 1.0</parameters>
</energy>
</source>
<electron_treatment>ttb</electron_treatment>
<photon_transport>true</photon_transport>
<cutoff>
<energy_photon>1000.0</energy_photon>
</cutoff>
</settings>
<tallies>
<filter id="1" type="surface">
<bins>1</bins>
</filter>
<filter id="2" type="particle">
<bins>neutron photon electron positron</bins>
</filter>
<filter id="5" type="particle">
<bins>neutron</bins>
</filter>
<filter id="3" type="energy">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="4" type="particleproduction">
<particles>neutron photon</particles>
<energies>0.0 100000.0 300000.0 500000.0 2000000.0 20000000.0</energies>
</filter>
<tally id="1">
<filters>1 2</filters>
<scores>current</scores>
</tally>
<tally id="2">
<filters>2</filters>
<nuclides>Al27 total</nuclides>
<scores>total (n,gamma)</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>2</filters>
<nuclides>Al27 total</nuclides>
<scores>total heating (n,gamma)</scores>
<estimator>collision</estimator>
</tally>
<tally id="4">
<filters>2</filters>
<nuclides>Al27 total</nuclides>
<scores>total heating (n,gamma)</scores>
<estimator>analog</estimator>
</tally>
<tally id="5">
<filters>5 3 4</filters>
<scores>events</scores>
<estimator>analog</estimator>
</tally>
</tallies>
</model>