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49 lines
2.1 KiB
XML
49 lines
2.1 KiB
XML
<?xml version="1.0"?>
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<depletion_chain>
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<nuclide name="I135" decay_modes="1" reactions="1" half_life="2.36520E+04">
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<decay type="beta" target="Xe135" branching_ratio="1.0" />
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<reaction type="(n,gamma)" Q="0.0" target="Xe136" /> <!-- Not precisely true, but whatever -->
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</nuclide>
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<nuclide name="Xe135" decay_modes="1" reactions="1" half_life="3.29040E+04">
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<decay type=" beta" target="Cs135" branching_ratio="1.0" />
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<reaction type="(n,gamma)" Q="0.0" target="Xe136" />
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</nuclide>
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<nuclide name="Xe136" decay_modes="0" reactions="0" />
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<nuclide name="Cs135" decay_modes="0" reactions="0" />
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<nuclide name="Gd157" decay_modes="0" reactions="1" >
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<reaction type="(n,gamma)" Q="0.0" target="Nothing" />
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</nuclide>
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<nuclide name="Gd156" decay_modes="0" reactions="1">
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<reaction type="(n,gamma)" Q="0.0" target="Gd157" />
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</nuclide>
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<nuclide name="U234" decay_modes="0" reactions="1">
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<reaction type="fission" Q="191840000."/>
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<neutron_fission_yields>
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<energies>2.53000e-02</energies>
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<fission_yields energy="2.53000e-02">
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<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
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<data>1.093250e-04 2.087260e-04 2.780820e-02 6.759540e-03 2.392300e-02 4.356330e-05</data>
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</fission_yields>
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</neutron_fission_yields>
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</nuclide>
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<nuclide name="U235" decay_modes="0" reactions="1">
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<reaction type="fission" Q="193410000."/>
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<neutron_fission_yields>
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<energies>2.53000e-02</energies>
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<fission_yields energy="2.53000e-02">
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<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
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<data>6.142710e-5 1.483250e-04 0.0292737 0.002566345 0.0219242 4.9097e-6</data>
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</fission_yields>
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</neutron_fission_yields>
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</nuclide>
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<nuclide name="U238" decay_modes="0" reactions="1">
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<reaction type="fission" Q="197790000."/>
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<neutron_fission_yields>
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<energies>2.53000e-02</energies>
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<fission_yields energy="2.53000e-02">
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<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
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<data>4.141120e-04 7.605360e-04 0.0135457 0.00026864 0.0024432 3.7100E-07</data>
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</fission_yields>
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</neutron_fission_yields>
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</nuclide>
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</depletion_chain>
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