OpenMC/tests/regression_tests/mgxs_library_specific_nuclides/inputs_true.dat

<?xml version='1.0' encoding='utf-8'?>
<model>
  <materials>
    <material id="1" name="UO2 (2.4%)" depletable="true">
      <density value="10.29769" units="g/cm3"/>
      <nuclide name="U234" ao="4.4843e-06"/>
      <nuclide name="U235" ao="0.00055815"/>
      <nuclide name="U238" ao="0.022408"/>
      <nuclide name="O16" ao="0.045829"/>
    </material>
    <material id="2" name="Zircaloy">
      <density value="6.55" units="g/cm3"/>
      <nuclide name="Zr90" ao="0.021827"/>
      <nuclide name="Zr91" ao="0.00476"/>
      <nuclide name="Zr92" ao="0.0072758"/>
      <nuclide name="Zr94" ao="0.0073734"/>
      <nuclide name="Zr96" ao="0.0011879"/>
    </material>
    <material id="3" name="Hot borated water">
      <density value="0.740582" units="g/cm3"/>
      <nuclide name="H1" ao="0.049457"/>
      <nuclide name="O16" ao="0.024672"/>
      <nuclide name="B10" ao="8.0042e-06"/>
      <nuclide name="B11" ao="3.2218e-05"/>
      <sab name="c_H_in_H2O"/>
    </material>
  </materials>
  <geometry>
    <cell id="1" name="Fuel" material="1" region="-1" universe="0"/>
    <cell id="2" name="Cladding" material="2" region="1 -2" universe="0"/>
    <cell id="3" name="Water" material="3" region="2 3 -4 5 -6" universe="0"/>
    <surface id="1" name="Fuel OR" type="z-cylinder" coeffs="0 0 0.39218"/>
    <surface id="2" name="Clad OR" type="z-cylinder" coeffs="0 0 0.4572"/>
    <surface id="3" name="left" type="x-plane" boundary="reflective" coeffs="-0.63"/>
    <surface id="4" name="right" type="x-plane" boundary="reflective" coeffs="0.63"/>
    <surface id="5" name="bottom" type="y-plane" boundary="reflective" coeffs="-0.63"/>
    <surface id="6" name="top" type="y-plane" boundary="reflective" coeffs="0.63"/>
  </geometry>
  <settings>
    <run_mode>eigenvalue</run_mode>
    <particles>100</particles>
    <batches>10</batches>
    <inactive>5</inactive>
    <source type="independent" strength="1.0" particle="neutron">
      <space type="box">
        <parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
      </space>
      <constraints>
        <fissionable>true</fissionable>
      </constraints>
    </source>
  </settings>
  <tallies>
    <filter id="383" type="material">
      <bins>1 2 3</bins>
    </filter>
    <filter id="2" type="energy">
      <bins>0.0 0.625 20000000.0</bins>
    </filter>
    <filter id="1" type="material">
      <bins>1</bins>
    </filter>
    <filter id="5" type="energyout">
      <bins>0.0 0.625 20000000.0</bins>
    </filter>
    <filter id="6" type="legendre">
      <order>1</order>
    </filter>
    <filter id="30" type="legendre">
      <order>3</order>
    </filter>
    <filter id="54" type="energy">
      <bins>0.0 20000000.0</bins>
    </filter>
    <filter id="106" type="material">
      <bins>2</bins>
    </filter>
    <filter id="251" type="material">
      <bins>3</bins>
    </filter>
    <tally id="528">
      <filters>383 2</filters>
      <nuclides>total</nuclides>
      <scores>flux</scores>
      <estimator>tracklength</estimator>
    </tally>
    <tally id="167">
      <filters>1 2</filters>
      <nuclides>U235 total</nuclides>
      <scores>total absorption (n,2n) (n,3n) (n,4n) fission nu-fission kappa-fission scatter inverse-velocity prompt-nu-fission (n,elastic) (n,level) (n,na) (n,nc) (n,gamma) (n,a) (n,Xa) heating damage-energy (n,n1) (n,a0)</scores>
      <estimator>tracklength</estimator>
    </tally>
    <tally id="540">
      <filters>383 2</filters>
      <nuclides>total</nuclides>
      <scores>flux</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="119">
      <filters>1 5 6</filters>
      <nuclides>U235 total</nuclides>
      <scores>scatter nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="54">
      <filters>1 2</filters>
      <nuclides>U235 total</nuclides>
      <scores>nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="84">
      <filters>1 2 5 30</filters>
      <nuclides>U235 total</nuclides>
      <scores>scatter nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="179">
      <filters>1 2 5</filters>
      <nuclides>U235 total</nuclides>
      <scores>nu-scatter scatter nu-fission prompt-nu-fission (n,nc) (n,n1) (n,2n)</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="90">
      <filters>1 54</filters>
      <nuclides>U235 total</nuclides>
      <scores>nu-fission prompt-nu-fission</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="91">
      <filters>1 5</filters>
      <nuclides>U235 total</nuclides>
      <scores>nu-fission prompt-nu-fission</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="348">
      <filters>106 2</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>total absorption (n,2n) (n,3n) (n,4n) fission nu-fission kappa-fission scatter inverse-velocity prompt-nu-fission (n,elastic) (n,level) (n,na) (n,nc) (n,gamma) (n,a) (n,Xa) heating damage-energy (n,n1) (n,a0)</scores>
      <estimator>tracklength</estimator>
    </tally>
    <tally id="300">
      <filters>106 5 6</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>scatter nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="235">
      <filters>106 2</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="265">
      <filters>106 2 5 30</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>scatter nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="360">
      <filters>106 2 5</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>nu-scatter scatter nu-fission prompt-nu-fission (n,nc) (n,n1) (n,2n)</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="271">
      <filters>106 54</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>nu-fission prompt-nu-fission</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="272">
      <filters>106 5</filters>
      <nuclides>Zr90 total</nuclides>
      <scores>nu-fission prompt-nu-fission</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="529">
      <filters>251 2</filters>
      <nuclides>H1 total</nuclides>
      <scores>total absorption (n,2n) (n,3n) (n,4n) fission nu-fission kappa-fission scatter inverse-velocity prompt-nu-fission (n,elastic) (n,level) (n,na) (n,nc) (n,gamma) (n,a) (n,Xa) heating damage-energy (n,n1) (n,a0)</scores>
      <estimator>tracklength</estimator>
    </tally>
    <tally id="481">
      <filters>251 5 6</filters>
      <nuclides>H1 total</nuclides>
      <scores>scatter nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="416">
      <filters>251 2</filters>
      <nuclides>H1 total</nuclides>
      <scores>nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="446">
      <filters>251 2 5 30</filters>
      <nuclides>H1 total</nuclides>
      <scores>scatter nu-scatter</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="541">
      <filters>251 2 5</filters>
      <nuclides>H1 total</nuclides>
      <scores>nu-scatter scatter nu-fission prompt-nu-fission (n,nc) (n,n1) (n,2n)</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="452">
      <filters>251 54</filters>
      <nuclides>H1 total</nuclides>
      <scores>nu-fission prompt-nu-fission</scores>
      <estimator>analog</estimator>
    </tally>
    <tally id="453">
      <filters>251 5</filters>
      <nuclides>H1 total</nuclides>
      <scores>nu-fission prompt-nu-fission</scores>
      <estimator>analog</estimator>
    </tally>
  </tallies>
</model>