OpenMC/tests/regression_tests/surface_source_write/case-e03/inputs_true.dat

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" depletable="true">
<density value="11.0" units="g/cm3"/>
<nuclide name="U234" ao="0.0004524"/>
<nuclide name="U235" ao="0.0506068"/>
<nuclide name="U238" ao="0.948709"/>
<nuclide name="U236" ao="0.0002318"/>
<nuclide name="O16" ao="2.0"/>
</material>
<material id="2">
<density value="1.0" units="g/cm3"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3" universe="1"/>
<cell id="2" material="2" region="1 | -2 | 3" universe="1"/>
<cell id="3" fill="1" region="-5 4 -7 6 -9 8" universe="2"/>
<surface id="1" type="z-cylinder" coeffs="0.0 0.0 2.0"/>
<surface id="2" type="z-plane" coeffs="-2.0"/>
<surface id="3" type="z-plane" coeffs="2.0"/>
<surface id="4" type="x-plane" boundary="vacuum" coeffs="-3.0"/>
<surface id="5" type="x-plane" boundary="vacuum" coeffs="3.0"/>
<surface id="6" type="y-plane" boundary="vacuum" coeffs="-3.0"/>
<surface id="7" type="y-plane" boundary="vacuum" coeffs="3.0"/>
<surface id="8" type="z-plane" boundary="vacuum" coeffs="-3.0"/>
<surface id="9" type="z-plane" boundary="vacuum" coeffs="3.0"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>1</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
<surf_source_write>
<surface_ids>4 5 6 7 8 9</surface_ids>
<max_particles>300</max_particles>
<cell>3</cell>
</surf_source_write>
<seed>1</seed>
</settings>
</model>