<?xml version='1.0' encoding='utf-8'?>
<geometry>
  <cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
  <surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
  <surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
  <surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
  <surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
  <surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
  <surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
  <material depletable="true" id="1" name="mat">
    <density units="atom/b-cm" value="0.069335" />
    <nuclide ao="40.0" name="H1" />
    <nuclide ao="1.0" name="U235" />
  </material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
  <run_mode>fixed source</run_mode>
  <particles>100</particles>
  <batches>10</batches>
  <source strength="1.0">
    <space type="box">
      <parameters>-1 -1 -1 1 1 1</parameters>
    </space>
    <energy parameters="988000.0 2.249e-06" type="watt" />
  </source>
  <create_fission_neutrons>false</create_fission_neutrons>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
  <tally id="1">
    <scores>flux</scores>
  </tally>
</tallies>
