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Merge pull request #2440 from paulromano/library-nuclide-hotfix

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Update reference inputs for mgxs_library_specific_nuclides test
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Ethan Peterson 2023-03-26 21:27:36 -04:00 • committed by GitHub
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tests/regression_tests/mgxs_library_specific_nuclides/inputs_true.dat
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@ -1,218 +1,217 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<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>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</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>