25-Mn-72
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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Mn- 72 U-235 Thermal 6.073650e-18 3.887140e-18
Mn- 72 U-235 Fast 1.188250e-16 7.604790e-17
Mn- 72 U-235 High 1.229360e-12 7.867950e-13
Mn- 72 U-238 Fast 1.945610e-15 1.245200e-15
Mn- 72 U-238 High 2.342120e-13 1.498960e-13
Mn- 72 Pu-239 Thermal 9.078030e-18 5.809950e-18
Mn- 72 Pu-239 Fast 1.834660e-16 1.174180e-16
Mn- 72 Pu-239 High 3.421060e-13 2.189480e-13
Mn- 72 Pu-241 Thermal 1.168000e-18 7.475190e-19
Mn- 72 Pu-241 Fast 1.360990e-16 8.710340e-17
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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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Mn- 72 U-235 Thermal 6.073650e-18 3.887140e-18
Mn- 72 U-235 Fast 1.188250e-16 7.604790e-17
Mn- 72 U-235 High 1.229360e-12 7.856300e-13
Mn- 72 U-238 Fast 1.945610e-15 1.244740e-15
Mn- 72 U-238 High 2.342120e-13 1.497330e-13
Mn- 72 Pu-239 Thermal 9.078030e-18 5.809950e-18
Mn- 72 Pu-239 Fast 1.834660e-16 1.174180e-16
Mn- 72 Pu-239 High 3.421060e-13 2.188060e-13
Mn- 72 Pu-241 Thermal 1.168000e-18 7.473980e-19
Mn- 72 Pu-241 Fast 1.360990e-16 8.710340e-17
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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