OpenMC/tests/regression_tests/stride/inputs_true.dat

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" depletable="true">
<density value="4.5" units="g/cm3"/>
<nuclide name="U235" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1"/>
<surface id="1" type="sphere" boundary="vacuum" coeffs="0.0 0.0 0.0 10.0"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
<stride>1529170</stride>
</settings>
</model>