47-Ag-131
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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Ag-131 U-235 Thermal 1.592040e-09 1.018910e-09
Ag-131 U-235 Fast 1.467490e-11 9.391940e-12
Ag-131 U-235 High 5.810020e-11 3.718420e-11
Ag-131 U-238 Fast 1.293390e-16 8.277720e-17
Ag-131 U-238 High 5.067870e-10 3.243440e-10
Ag-131 Pu-239 Thermal 4.492950e-12 2.875480e-12
Ag-131 Pu-239 Fast 5.512570e-12 3.528050e-12
Ag-131 Pu-241 Thermal 1.321370e-11 8.456780e-12
Ag-131 Pu-241 Fast 3.018990e-11 1.932160e-11
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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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Ag-131 U-235 Thermal 1.592040e-09 1.018910e-09
Ag-131 U-235 Fast 1.467490e-11 9.391940e-12
Ag-131 U-235 High 5.810020e-11 3.712910e-11
Ag-131 U-238 Fast 1.293390e-16 8.274690e-17
Ag-131 U-238 High 5.067870e-10 3.239920e-10
Ag-131 Pu-239 Thermal 4.492950e-12 2.875480e-12
Ag-131 Pu-239 Fast 5.512570e-12 3.528050e-12
Ag-131 Pu-241 Thermal 1.321370e-11 8.455410e-12
Ag-131 Pu-241 Fast 3.018990e-11 1.932160e-11
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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