60-Nd-162
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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Nd-162 U-235 Thermal 3.474430e-14 2.223640e-14
Nd-162 U-235 Fast 1.077760e-12 6.897680e-13
Nd-162 U-235 High 2.673670e-12 1.711150e-12
Nd-162 U-238 Fast 4.431480e-10 2.836150e-10
Nd-162 U-238 High 2.532250e-09 1.620640e-09
Nd-162 Pu-239 Thermal 1.749660e-12 1.119780e-12
Nd-162 Pu-239 Fast 2.089660e-12 1.337390e-12
Nd-162 Pu-239 High 7.194670e-13 4.604590e-13
Nd-162 Pu-241 Thermal 8.931230e-13 5.715990e-13
Nd-162 Pu-241 Fast 1.908510e-10 1.221450e-10
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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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Nd-162 U-235 Thermal 3.474460e-14 2.223660e-14
Nd-162 U-235 Fast 1.077780e-12 6.897770e-13
Nd-162 U-235 High 2.673670e-12 1.708610e-12
Nd-162 U-238 Fast 4.431650e-10 2.835220e-10
Nd-162 U-238 High 2.532760e-09 1.619210e-09
Nd-162 Pu-239 Thermal 1.749730e-12 1.119830e-12
Nd-162 Pu-239 Fast 2.089660e-12 1.337390e-12
Nd-162 Pu-239 High 7.194670e-13 4.601600e-13
Nd-162 Pu-241 Thermal 8.931440e-13 5.715200e-13
Nd-162 Pu-241 Fast 1.908560e-10 1.221480e-10
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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