OpenMC/tests/regression_tests/mg_tallies/inputs_true.dat

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XML

<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density value="1.0" units="macro"/>
<macroscopic name="mat_1"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0"/>
<surface id="1" type="x-plane" boundary="reflective" coeffs="0.0"/>
<surface id="2" type="x-plane" boundary="vacuum" coeffs="929.45"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>0.0 0.0 0.0</lower_left>
<upper_right>929.45 1000 1000</upper_right>
</mesh>
<filter id="5" type="mesh">
<bins>1</bins>
</filter>
<filter id="6" type="material">
<bins>1</bins>
</filter>
<filter id="1" type="energy">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="3" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="1">
<filters>5</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>5</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="5">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>6 1 2</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="7">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="9">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10">
<filters>6 3 4</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="11">
<filters>5</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="12">
<filters>5</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="15">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="16">
<filters>6 1 2</filters>
<nuclides>mat_1</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="17">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="19">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="20">
<filters>6 3 4</filters>
<nuclides>mat_1</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>
</model>