OpenMC/tests/regression_tests/distribmat/inputs_true.dat

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1">
<density value="1.0" units="g/cc"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
<material id="2" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="3" depletable="true">
<density value="2.0" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" universe="1"/>
<cell id="11" region="-1" universe="11">
<material>2 void 3 2</material>
</cell>
<cell id="12" material="1" region="1" universe="11"/>
<cell id="101" fill="101" region="2 -3 4 -5" universe="0"/>
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 11
11 11 </universes>
</lattice>
<surface id="1" type="z-cylinder" coeffs="0.0 0.0 0.3"/>
<surface id="2" type="x-plane" boundary="reflective" coeffs="-3.0"/>
<surface id="3" type="x-plane" boundary="reflective" coeffs="3.0"/>
<surface id="4" type="y-plane" boundary="reflective" coeffs="-3.0"/>
<surface id="5" type="y-plane" boundary="reflective" coeffs="3.0"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>
<plots>
<plot id="1" filename="cellplot" color_by="cell" type="slice" basis="xy">
<pixels>400 400</pixels>
<origin>0 0 0</origin>
<width>7 7</width>
</plot>
<plot id="2" filename="matplot" color_by="material" type="slice" basis="xy">
<pixels>400 400</pixels>
<origin>0 0 0</origin>
<width>7 7</width>
</plot>
</plots>
</model>