OpenMC/tests/regression_tests/surface_source_write/case-d01/inputs_true.dat
2024-06-22 01:28:56 +00:00

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="40" name="no-void fuel">
<density units="g/cc" value="11"/>
<nuclide ao="1.0" name="U235"/>
</material>
<material id="41" name="water">
<density units="g/cc" value="1.0"/>
<nuclide ao="2.0" name="H1"/>
<nuclide ao="1.0" name="O16"/>
<sab name="c_H_in_H2O"/>
</material>
</materials>
<geometry>
<dagmc_universe filename="../../dagmc/legacy/dagmc.h5m" id="1"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>1</inactive>
<source particle="neutron" strength="1.0" type="independent">
<space type="box">
<parameters>-4 -4 -20 4 4 20</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
<surf_source_write>
<max_particles>300</max_particles>
</surf_source_write>
<seed>1</seed>
</settings>
</model>