mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-23 19:45:34 -04:00
30 lines
851 B
XML
30 lines
851 B
XML
<?xml version='1.0' encoding='utf-8'?>
|
|
<model>
|
|
<materials>
|
|
<material depletable="true" id="1">
|
|
<density units="g/cc" value="7.5"/>
|
|
<nuclide ao="1.0" name="O16"/>
|
|
<nuclide ao="0.0001" name="U238"/>
|
|
</material>
|
|
</materials>
|
|
<geometry>
|
|
<cell id="1" material="1" region="-1" universe="1"/>
|
|
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 10.0" id="1" type="sphere"/>
|
|
</geometry>
|
|
<settings>
|
|
<run_mode>fixed source</run_mode>
|
|
<particles>100</particles>
|
|
<batches>10</batches>
|
|
<source particle="neutron" strength="10.0" type="independent">
|
|
<space type="point">
|
|
<parameters>0.0 0.0 0.0</parameters>
|
|
</space>
|
|
</source>
|
|
<temperature_default>294</temperature_default>
|
|
</settings>
|
|
<tallies>
|
|
<tally id="1">
|
|
<scores>flux</scores>
|
|
</tally>
|
|
</tallies>
|
|
</model>
|