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82 lines
2.6 KiB
XML
82 lines
2.6 KiB
XML
<?xml version='1.0' encoding='utf-8'?>
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<model>
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<materials>
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<material id="1">
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<density value="2.6989" units="g/cm3"/>
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<nuclide name="Al27" ao="1.0"/>
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</material>
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</materials>
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<geometry>
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<cell id="1" material="void" region="-1 2 -3" universe="1"/>
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<cell id="2" material="1" region="-1 3 -4" universe="1"/>
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<cell id="3" material="void" region="1 | -2 | 4" universe="1"/>
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<surface id="1" type="x-cylinder" boundary="vacuum" coeffs="0.0 0.0 1.0"/>
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<surface id="2" type="x-plane" boundary="vacuum" coeffs="-1.0"/>
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<surface id="3" type="x-plane" coeffs="1.0"/>
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<surface id="4" type="x-plane" boundary="vacuum" coeffs="1000000000.0"/>
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</geometry>
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<settings>
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<run_mode>fixed source</run_mode>
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<particles>10000</particles>
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<batches>1</batches>
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<source type="independent" strength="1.0" particle="neutron">
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<space type="point">
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<parameters>0 0 0</parameters>
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</space>
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<angle type="monodirectional" reference_uvw="1.0 0.0 0.0"/>
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<energy type="discrete">
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<parameters>14000000.0 1.0</parameters>
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</energy>
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</source>
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<electron_treatment>ttb</electron_treatment>
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<photon_transport>true</photon_transport>
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<cutoff>
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<energy_photon>1000.0</energy_photon>
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</cutoff>
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</settings>
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<tallies>
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<filter id="1" type="surface">
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<bins>1</bins>
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</filter>
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<filter id="2" type="particle">
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<bins>neutron photon electron positron</bins>
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</filter>
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<filter id="5" type="particle">
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<bins>neutron</bins>
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</filter>
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<filter id="3" type="energy">
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<bins>0.0 20000000.0</bins>
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</filter>
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<filter id="4" type="particleproduction">
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<particles>neutron photon</particles>
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<energies>0.0 100000.0 300000.0 500000.0 2000000.0 20000000.0</energies>
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</filter>
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<tally id="1">
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<filters>1 2</filters>
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<scores>current</scores>
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</tally>
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<tally id="2">
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<filters>2</filters>
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<nuclides>Al27 total</nuclides>
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<scores>total (n,gamma)</scores>
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<estimator>tracklength</estimator>
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</tally>
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<tally id="3">
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<filters>2</filters>
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<nuclides>Al27 total</nuclides>
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<scores>total heating (n,gamma)</scores>
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<estimator>collision</estimator>
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</tally>
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<tally id="4">
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<filters>2</filters>
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<nuclides>Al27 total</nuclides>
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<scores>total heating (n,gamma)</scores>
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<estimator>analog</estimator>
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</tally>
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<tally id="5">
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<filters>5 3 4</filters>
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<scores>events</scores>
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<estimator>analog</estimator>
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</tally>
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</tallies>
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</model>
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