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