<?xml version='1.0' encoding='utf-8'?>
<geometry>
  <cell id="1" material="1" region="1 -2" universe="0" />
  <surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
  <surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
  <cross_sections>2g.h5</cross_sections>
  <material id="1" name="mat_1">
    <density units="macro" value="1.0" />
    <macroscopic name="mat_1" />
  </material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
  <run_mode>eigenvalue</run_mode>
  <particles>1000</particles>
  <batches>10</batches>
  <inactive>5</inactive>
  <source strength="1.0">
    <space type="box">
      <parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
    </space>
  </source>
  <output>
    <summary>false</summary>
  </output>
  <energy_mode>multi-group</energy_mode>
  <tabular_legendre>
    <enable>false</enable>
  </tabular_legendre>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
  <mesh id="1">
    <dimension>10 1 1</dimension>
    <lower_left>0.0 0.0 0.0</lower_left>
    <upper_right>929.45 1000 1000</upper_right>
  </mesh>
  <filter id="5" type="mesh">
    <bins>1</bins>
  </filter>
  <filter id="6" type="material">
    <bins>1</bins>
  </filter>
  <filter id="1" type="energy">
    <bins>0.0 20000000.0</bins>
  </filter>
  <filter id="2" type="energyout">
    <bins>0.0 20000000.0</bins>
  </filter>
  <filter id="3" type="energy">
    <bins>0.0 0.625 20000000.0</bins>
  </filter>
  <filter id="4" type="energyout">
    <bins>0.0 0.625 20000000.0</bins>
  </filter>
  <tally id="1">
    <filters>5</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
    <estimator>analog</estimator>
  </tally>
  <tally id="2">
    <filters>5</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
    <estimator>tracklength</estimator>
  </tally>
  <tally id="3">
    <filters>6 1</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
    <estimator>analog</estimator>
  </tally>
  <tally id="4">
    <filters>6 1</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
    <estimator>collision</estimator>
  </tally>
  <tally id="5">
    <filters>6 1</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
    <estimator>tracklength</estimator>
  </tally>
  <tally id="6">
    <filters>6 1 2</filters>
    <scores>scatter nu-scatter nu-fission</scores>
  </tally>
  <tally id="7">
    <filters>6 3</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
    <estimator>analog</estimator>
  </tally>
  <tally id="8">
    <filters>6 3</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
    <estimator>collision</estimator>
  </tally>
  <tally id="9">
    <filters>6 3</filters>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
    <estimator>tracklength</estimator>
  </tally>
  <tally id="10">
    <filters>6 3 4</filters>
    <scores>scatter nu-scatter nu-fission</scores>
  </tally>
  <tally id="11">
    <filters>5</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
    <estimator>analog</estimator>
  </tally>
  <tally id="12">
    <filters>5</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
    <estimator>tracklength</estimator>
  </tally>
  <tally id="13">
    <filters>6 1</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
    <estimator>analog</estimator>
  </tally>
  <tally id="14">
    <filters>6 1</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
    <estimator>collision</estimator>
  </tally>
  <tally id="15">
    <filters>6 1</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
    <estimator>tracklength</estimator>
  </tally>
  <tally id="16">
    <filters>6 1 2</filters>
    <nuclides>mat_1</nuclides>
    <scores>scatter nu-scatter nu-fission</scores>
  </tally>
  <tally id="17">
    <filters>6 3</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
    <estimator>analog</estimator>
  </tally>
  <tally id="18">
    <filters>6 3</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
    <estimator>collision</estimator>
  </tally>
  <tally id="19">
    <filters>6 3</filters>
    <nuclides>mat_1</nuclides>
    <scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
    <estimator>tracklength</estimator>
  </tally>
  <tally id="20">
    <filters>6 3 4</filters>
    <nuclides>mat_1</nuclides>
    <scores>scatter nu-scatter nu-fission</scores>
  </tally>
</tallies>
