<?xml version='1.0' encoding='utf-8'?>
<model>
  <materials>
    <material depletable="true" id="1">
      <density units="g/cc" value="1.0"/>
      <nuclide ao="1.0" name="U238"/>
      <nuclide ao="0.02" name="U235"/>
      <nuclide ao="0.02" name="Pu239"/>
      <nuclide ao="20.0" name="H1"/>
    </material>
  </materials>
  <geometry>
    <cell id="1" material="1" region="-1" universe="0"/>
    <surface boundary="reflective" coeffs="100" id="1" type="x-plane"/>
  </geometry>
  <settings>
    <run_mode>eigenvalue</run_mode>
    <particles>1000</particles>
    <batches>10</batches>
    <inactive>5</inactive>
    <source particle="neutron" strength="1.0" type="independent">
      <space type="box">
        <parameters>-4 -4 -4 4 4 4</parameters>
      </space>
    </source>
    <resonance_scattering>
      <enable>true</enable>
      <method>rvs</method>
      <energy_min>1.0</energy_min>
      <energy_max>210.0</energy_max>
      <nuclides>U238 U235 Pu239</nuclides>
    </resonance_scattering>
  </settings>
  </model>
