mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-26 05:05:30 -04:00
36 lines
1.3 KiB
XML
36 lines
1.3 KiB
XML
<?xml version='1.0' encoding='utf-8'?>
|
|
<model>
|
|
<materials>
|
|
<material id="1" name="mat" depletable="true">
|
|
<density value="0.069335" units="atom/b-cm"/>
|
|
<nuclide name="H1" ao="40.0"/>
|
|
<nuclide name="U235" ao="1.0"/>
|
|
</material>
|
|
</materials>
|
|
<geometry>
|
|
<cell id="1" name="box" material="1" region="1 -2 3 -4 5 -6" universe="0"/>
|
|
<surface id="1" type="x-plane" boundary="reflective" coeffs="-1"/>
|
|
<surface id="2" type="x-plane" boundary="reflective" coeffs="1"/>
|
|
<surface id="3" type="y-plane" boundary="reflective" coeffs="-1"/>
|
|
<surface id="4" type="y-plane" boundary="reflective" coeffs="1"/>
|
|
<surface id="5" type="z-plane" boundary="reflective" coeffs="-1"/>
|
|
<surface id="6" type="z-plane" boundary="reflective" coeffs="1"/>
|
|
</geometry>
|
|
<settings>
|
|
<run_mode>fixed source</run_mode>
|
|
<particles>100</particles>
|
|
<batches>10</batches>
|
|
<source type="independent" strength="1.0" particle="neutron">
|
|
<space type="box">
|
|
<parameters>-1 -1 -1 1 1 1</parameters>
|
|
</space>
|
|
<energy type="watt" parameters="988000.0 2.249e-06"/>
|
|
</source>
|
|
<create_fission_neutrons>false</create_fission_neutrons>
|
|
</settings>
|
|
<tallies>
|
|
<tally id="1">
|
|
<scores>flux</scores>
|
|
</tally>
|
|
</tallies>
|
|
</model>
|