27-Co-77
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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Co- 77 U-235 Thermal 6.516510e-15 4.170560e-15
Co- 77 U-235 Fast 6.122040e-14 3.918110e-14
Co- 77 U-235 High 2.277700e-11 1.457720e-11
Co- 77 U-238 Fast 6.025640e-12 3.856400e-12
Co- 77 U-238 High 7.349420e-12 4.703630e-12
Co- 77 Pu-239 Thermal 1.657830e-15 1.061010e-15
Co- 77 Pu-239 Fast 9.837100e-15 6.295740e-15
Co- 77 Pu-239 High 7.588930e-12 4.856910e-12
Co- 77 Pu-241 Thermal 3.798950e-16 2.431320e-16
Co- 77 Pu-241 Fast 2.437830e-14 1.560210e-14
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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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Co- 77 U-235 Thermal 6.516510e-15 4.170560e-15
Co- 77 U-235 Fast 6.122040e-14 3.918110e-14
Co- 77 U-235 High 2.277700e-11 1.455560e-11
Co- 77 U-238 Fast 6.025640e-12 3.855190e-12
Co- 77 U-238 High 7.349420e-12 4.698540e-12
Co- 77 Pu-239 Thermal 1.657830e-15 1.061010e-15
Co- 77 Pu-239 Fast 9.837100e-15 6.295740e-15
Co- 77 Pu-239 High 7.588930e-12 4.853760e-12
Co- 77 Pu-241 Thermal 3.798950e-16 2.430930e-16
Co- 77 Pu-241 Fast 2.437830e-14 1.560210e-14
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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