OpenMC/tests/regression_tests/cpp_driver/inputs_true.dat

Ignoring revisions in .git-blame-ignore-revs. Click here to bypass and see the normal blame view.

46 lines
1.6 KiB
Text
Raw Normal View History

<?xml version='1.0' encoding='utf-8'?>
<geometry>
2020-05-13 17:05:31 -05:00
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1 -2" universe="1" />
<cell id="3" material="3" region="2" universe="1" />
<cell fill="1" id="4" universe="2" />
<cell fill="3" id="5" region="3 -4 5 -6" universe="4" />
<lattice id="3">
<pitch>4.0 4.0</pitch>
<dimension>2 2</dimension>
<lower_left>-4.0 -4.0</lower_left>
<universes>
2 2
2 2 </universes>
</lattice>
2020-05-13 17:05:31 -05:00
<surface coeffs="0.0 0.0 1.5" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 1.7" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-4.0" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="4.0" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-4.0" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="4.0" id="6" name="maximum y" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
2020-05-13 17:05:31 -05:00
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="cladding">
<density units="g/cc" value="6.44" />
<nuclide ao="1.0" name="Zr90" />
</material>
<material id="3" name="water">
2020-05-13 17:05:31 -05:00
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>1</inactive>
</settings>