<?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>
