49-In-136
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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In-136 U-235 Thermal 1.677330e-12 1.073490e-12
In-136 U-235 Fast 6.855850e-12 4.387740e-12
In-136 U-235 High 1.331830e-11 8.523690e-12
In-136 U-238 Fast 2.701010e-09 1.728640e-09
In-136 U-238 High 6.487070e-10 4.151720e-10
In-136 Pu-239 Thermal 2.819560e-13 1.804520e-13
In-136 Pu-239 Fast 5.209160e-13 3.333860e-13
In-136 Pu-239 High 6.854450e-12 4.386850e-12
In-136 Pu-241 Thermal 1.050170e-11 6.721080e-12
In-136 Pu-241 Fast 2.028470e-11 1.298220e-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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In-136 U-235 Thermal 1.677330e-12 1.073490e-12
In-136 U-235 Fast 6.855850e-12 4.387740e-12
In-136 U-235 High 1.331830e-11 8.511060e-12
In-136 U-238 Fast 2.701040e-09 1.728010e-09
In-136 U-238 High 6.487190e-10 4.147230e-10
In-136 Pu-239 Thermal 2.819560e-13 1.804520e-13
In-136 Pu-239 Fast 5.209160e-13 3.333860e-13
In-136 Pu-239 High 6.854450e-12 4.384000e-12
In-136 Pu-241 Thermal 1.050170e-11 6.719990e-12
In-136 Pu-241 Fast 2.028470e-11 1.298220e-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