<?xml version='1.0' encoding='utf-8'?>
<model>
  <materials>
    <cross_sections>mgxs.h5</cross_sections>
    <material id="1" name="UO2 fuel">
      <density units="macro" value="1.1"/>
      <macroscopic name="UO2"/>
    </material>
  </materials>
  <geometry>
    <cell id="1" material="1" name="cell 1" region="4 -5 6 -7" universe="0"/>
    <surface boundary="reflective" coeffs="-5.0" id="4" name="left" type="x-plane"/>
    <surface boundary="vacuum" coeffs="5.0" id="5" name="right" type="x-plane"/>
    <surface boundary="reflective" coeffs="-5.0" id="6" name="bottom" type="y-plane"/>
    <surface boundary="reflective" coeffs="5.0" id="7" name="top" type="y-plane"/>
  </geometry>
  <settings>
    <run_mode>eigenvalue</run_mode>
    <particles>100</particles>
    <batches>10</batches>
    <inactive>5</inactive>
    <source particle="neutron" strength="1.0" type="independent">
      <space type="box">
        <parameters>-5 -5 -5 5 5 5</parameters>
      </space>
    </source>
    <energy_mode>multi-group</energy_mode>
  </settings>
  </model>
