<?xml version='1.0' encoding='utf-8'?>
<model>
  <materials>
    <material depletable="true" id="1">
      <density units="g/cm3" value="4.5"/>
      <nuclide ao="1.0" name="U235"/>
    </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>eigenvalue</run_mode>
    <particles>1000</particles>
    <batches>7</batches>
    <inactive>3</inactive>
    <generations_per_batch>3</generations_per_batch>
    <source particle="neutron" strength="1.0" type="independent">
      <space type="box">
        <parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
      </space>
    </source>
  </settings>
  <tallies>
    <tally id="1">
      <scores>flux</scores>
    </tally>
  </tallies>
</model>
