OpenMC/tests/regression_tests/energy_cutoff/inputs_true.dat
Patrick Shriwise eda39ad9ca
Python source class refactor (#2524)
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
2023-06-20 21:27:55 -05:00

41 lines
1.3 KiB
XML

<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335"/>
<nuclide ao="40.0" name="H1"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0"/>
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane"/>
<surface boundary="reflective" coeffs="1" id="2" type="x-plane"/>
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane"/>
<surface boundary="reflective" coeffs="1" id="4" type="y-plane"/>
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane"/>
<surface boundary="reflective" coeffs="1" id="6" type="z-plane"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source particle="neutron" strength="1.0" type="independent">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt"/>
</source>
<cutoff>
<energy_neutron>4.0</energy_neutron>
</cutoff>
</settings>
<tallies>
<filter id="1" type="energy">
<bins>0.0 4.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>