<?xml version='1.0' encoding='utf-8'?>
<model>
  <materials>
    <material depletable="true" id="40" name="no-void fuel">
      <density units="g/cc" value="11"/>
      <nuclide ao="1.0" name="U235"/>
    </material>
    <material id="41" name="water">
      <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>
  </materials>
  <geometry>
    <dagmc_universe filename="dagmc.h5m" id="1"/>
  </geometry>
  <settings>
    <run_mode>eigenvalue</run_mode>
    <particles>100</particles>
    <batches>5</batches>
    <inactive>0</inactive>
    <source particle="neutron" strength="1.0" type="independent">
      <space type="box">
        <parameters>-4 -4 -4 4 4 4</parameters>
      </space>
    </source>
    <temperature_default>293</temperature_default>
  </settings>
  <tallies>
    <filter id="1" type="cell">
      <bins>1</bins>
    </filter>
    <tally id="1">
      <filters>1</filters>
      <scores>total</scores>
    </tally>
  </tallies>
</model>
