48-Cd-134
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data
- Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Cd-134 U-235 Thermal 9.315170e-13 5.961710e-13
Cd-134 U-235 Fast 3.013770e-12 1.928810e-12
Cd-134 U-235 High 2.062830e-12 1.320210e-12
Cd-134 U-238 Fast 9.373490e-10 5.999040e-10
Cd-134 U-238 High 1.081170e-10 6.919540e-11
Cd-134 Pu-239 Thermal 2.139660e-13 1.369380e-13
Cd-134 Pu-239 Fast 1.839700e-13 1.177410e-13
Cd-134 Pu-239 High 1.230800e-12 7.877110e-13
Cd-134 Pu-241 Thermal 2.620420e-12 1.677070e-12
Cd-134 Pu-241 Fast 4.896320e-12 3.133640e-12
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
- Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Cd-134 U-235 Thermal 9.315170e-13 5.961710e-13
Cd-134 U-235 Fast 3.013770e-12 1.928810e-12
Cd-134 U-235 High 2.062830e-12 1.318250e-12
Cd-134 U-238 Fast 9.373490e-10 5.996840e-10
Cd-134 U-238 High 1.081170e-10 6.912040e-11
Cd-134 Pu-239 Thermal 2.139660e-13 1.369380e-13
Cd-134 Pu-239 Fast 1.839700e-13 1.177410e-13
Cd-134 Pu-239 High 1.230800e-12 7.872000e-13
Cd-134 Pu-241 Thermal 2.620420e-12 1.676800e-12
Cd-134 Pu-241 Fast 4.896320e-12 3.133640e-12
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
→ Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data