OpenMC/tests/regression_tests/model_xml/inputs_true.dat
2023-05-09 10:41:04 -05:00

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XML

<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="6">
<density units="g/cm3" value="2.6989"/>
<nuclide ao="1.0" name="Al27"/>
</material>
</materials>
<geometry>
<cell id="12" material="void" region="-16 17 -18" universe="10"/>
<cell id="13" material="6" region="-16 18 -19" universe="10"/>
<cell id="14" material="void" region="~(-16 17 -19)" universe="10"/>
<surface id="16" type="x-cylinder" boundary="vacuum" coeffs="0.0 0.0 1.0"/>
<surface id="17" type="x-plane" boundary="vacuum" coeffs="-1.0"/>
<surface id="18" type="x-plane" coeffs="1.0"/>
<surface id="19" type="x-plane" boundary="vacuum" coeffs="1000000000.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>10000</particles>
<batches>1</batches>
<source strength="1.0">
<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>16</bins>
</filter>
<filter id="2" type="particle">
<bins>neutron photon electron positron</bins>
</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>
</tallies>
</model>