53-I-146
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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I-146 U-235 Thermal 9.004290e-13 5.762750e-13
I-146 U-235 Fast 3.775740e-12 2.416470e-12
I-146 U-235 High 2.555570e-11 1.635570e-11
I-146 U-238 Fast 7.758850e-09 4.965670e-09
I-146 U-238 High 6.945600e-10 4.445190e-10
I-146 Pu-239 Thermal 6.091840e-13 3.898770e-13
I-146 Pu-239 Fast 3.814480e-13 2.441270e-13
I-146 Pu-241 Thermal 9.603540e-12 6.146270e-12
I-146 Pu-241 Fast 7.552610e-12 4.833670e-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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I-146 U-235 Thermal 9.004290e-13 5.762750e-13
I-146 U-235 Fast 3.775740e-12 2.416470e-12
I-146 U-235 High 2.555570e-11 1.633140e-11
I-146 U-238 Fast 7.758850e-09 4.964130e-09
I-146 U-238 High 6.945600e-10 4.440380e-10
I-146 Pu-239 Thermal 6.091840e-13 3.898770e-13
I-146 Pu-239 Fast 3.814480e-13 2.441270e-13
I-146 Pu-241 Thermal 9.603540e-12 6.145270e-12
I-146 Pu-241 Fast 7.552610e-12 4.833670e-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