OpenMC/tests/regression_tests/dagmc/universes/inputs_true.dat
Ilham Variansyah ecb0a3361f
Combing for fission site sampling, and delayed neutron emission time (#2992)
Co-authored-by: Gavin Ridley <gavin.keith.ridley@gmail.com>
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
2025-09-19 08:10:08 +00:00

72 lines
2.5 KiB
XML

<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="no-void fuel" depletable="true">
<density value="10.29769" units="g/cc"/>
<nuclide name="U234" ao="0.93120485"/>
<nuclide name="U235" ao="0.00055815"/>
<nuclide name="U238" ao="0.022408"/>
<nuclide name="O16" ao="0.045829"/>
</material>
<material id="2" name="clad">
<density value="6.55" units="g/cc"/>
<nuclide name="Zr90" ao="0.021827"/>
<nuclide name="Zr91" ao="0.00476"/>
<nuclide name="Zr92" ao="0.0072758"/>
<nuclide name="Zr94" ao="0.0073734"/>
<nuclide name="Zr96" ao="0.0011879"/>
</material>
<material id="3" name="water">
<density value="0.740582" units="g/cc"/>
<nuclide name="H1" ao="0.049457"/>
<nuclide name="O16" ao="0.024672"/>
<nuclide name="B10" ao="8.0042e-06"/>
<nuclide name="B11" ao="3.2218e-05"/>
<sab name="c_H_in_H2O"/>
</material>
</materials>
<geometry>
<cell id="1" fill="4" region="1 -2 3 -4 5 -6" universe="5"/>
<dagmc_universe id="1" auto_geom_ids="true" filename="dagmc.h5m"/>
<lattice id="4">
<pitch>24.0 24.0</pitch>
<dimension>2 2</dimension>
<lower_left>-24.0 -24.0</lower_left>
<universes>
1 1
1 1 </universes>
</lattice>
<surface id="1" name="left" type="x-plane" boundary="reflective" coeffs="-24.0"/>
<surface id="2" name="right" type="x-plane" boundary="reflective" coeffs="24.0"/>
<surface id="3" name="front" type="y-plane" boundary="reflective" coeffs="-24.0"/>
<surface id="4" name="back" type="y-plane" boundary="reflective" coeffs="24.0"/>
<surface id="5" name="bottom" type="z-plane" boundary="reflective" coeffs="-10.0"/>
<surface id="6" name="top" type="z-plane" boundary="reflective" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-10.0 -10.0 -24.0 10.0 10.0 24.0</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
<output>
<summary>false</summary>
</output>
</settings>
<tallies>
<filter id="1" type="cellinstance">
<bins>4 0 4 1 4 2 4 3 4 4</bins>
</filter>
<tally id="1" name="cell instance tally">
<filters>1</filters>
<scores>scatter</scores>
</tally>
</tallies>
</model>