<?xml version='1.0' encoding='utf-8'?>
<geometry>
  <cell id="1" material="1" universe="1" />
  <cell id="11" material="2" region="-1" temperature="500 700 0 800" universe="11" />
  <cell id="12" material="1" region="1" universe="11" />
  <cell fill="101" id="101" region="2 -3 4 -5" universe="0" />
  <lattice id="101">
    <pitch>2.0 2.0</pitch>
    <outer>1</outer>
    <dimension>2 2</dimension>
    <lower_left>-2.0 -2.0</lower_left>
    <universes>
11 11 
11 11 </universes>
  </lattice>
  <surface coeffs="0.0 0.0 0.3" id="1" type="z-cylinder" />
  <surface boundary="reflective" coeffs="-3.0" id="2" type="x-plane" />
  <surface boundary="reflective" coeffs="3.0" id="3" type="x-plane" />
  <surface boundary="reflective" coeffs="-3.0" id="4" type="y-plane" />
  <surface boundary="reflective" coeffs="3.0" id="5" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
  <material id="1">
    <density units="g/cc" value="1.0" />
    <nuclide ao="2.0" name="H1" />
    <nuclide ao="1.0" name="O16" />
    <sab name="c_H_in_H2O" />
  </material>
  <material depletable="true" id="2">
    <density units="g/cc" value="4.5" />
    <nuclide ao="1.0" name="U235" />
  </material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
  <run_mode>eigenvalue</run_mode>
  <particles>1000</particles>
  <batches>5</batches>
  <inactive>0</inactive>
  <source strength="1.0">
    <space type="box">
      <parameters>-1 -1 -1 1 1 1</parameters>
    </space>
  </source>
  <temperature_multipole>true</temperature_multipole>
  <temperature_tolerance>1000</temperature_tolerance>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
  <tally id="1">
    <nuclides>U235 O16 total</nuclides>
    <scores>total fission (n,gamma) elastic (n,p)</scores>
  </tally>
</tallies>
