<?xml version='1.0' encoding='utf-8'?>
<model>
  <materials>
    <material depletable="true" id="1">
      <density units="g/cc" value="19.0" />
      <nuclide name="U235" wo="0.21" />
      <nuclide name="U238" wo="0.68" />
      <nuclide name="O16" wo="0.11" />
    </material>
  </materials>
  <geometry>
    <cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
    <surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
    <surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
    <surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
    <surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
    <surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
    <surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
  </geometry>
  <settings>
    <run_mode>eigenvalue</run_mode>
    <particles>1000</particles>
    <batches>20</batches>
    <inactive>10</inactive>
    <source strength="1.0">
      <space type="box">
        <parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
      </space>
    </source>
    <state_point>
      <batches>15 20</batches>
    </state_point>
    <entropy_mesh>10</entropy_mesh>
    <mesh id="10">
      <dimension>10 1 1</dimension>
      <lower_left>-10.0 -1.0 -1.0</lower_left>
      <upper_right>10.0 1.0 1.0</upper_right>
    </mesh>
  </settings>
  <tallies>
    <mesh id="1">
      <dimension>10 1 1</dimension>
      <lower_left>-10.0 -1.0 -1.0</lower_left>
      <upper_right>10.0 1.0 1.0</upper_right>
    </mesh>
    <filter id="1" type="mesh">
      <bins>1</bins>
    </filter>
    <tally id="1">
      <filters>1</filters>
      <scores>flux</scores>
    </tally>
  </tallies>
</model>
