24-Cr-69
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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Cr- 69 U-235 Thermal 2.104990e-18 1.347190e-18
Cr- 69 U-235 Fast 2.888800e-17 1.848830e-17
Cr- 69 U-235 High 6.567860e-13 4.203430e-13
Cr- 69 U-238 Fast 6.894380e-14 4.412410e-14
Cr- 69 U-238 High 7.934960e-14 5.078370e-14
Cr- 69 Pu-239 Thermal 1.901130e-18 1.216720e-18
Cr- 69 Pu-239 Fast 4.849480e-17 3.103660e-17
Cr- 69 Pu-239 High 2.058300e-13 1.317310e-13
Cr- 69 Pu-241 Thermal 5.815890e-19 3.722170e-19
Cr- 69 Pu-241 Fast 3.344920e-17 2.140750e-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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Cr- 69 U-235 Thermal 2.104990e-18 1.347190e-18
Cr- 69 U-235 Fast 2.888800e-17 1.848830e-17
Cr- 69 U-235 High 6.567860e-13 4.197200e-13
Cr- 69 U-238 Fast 6.894380e-14 4.410970e-14
Cr- 69 U-238 High 7.934960e-14 5.072870e-14
Cr- 69 Pu-239 Thermal 1.901130e-18 1.216720e-18
Cr- 69 Pu-239 Fast 4.849480e-17 3.103660e-17
Cr- 69 Pu-239 High 2.058300e-13 1.316460e-13
Cr- 69 Pu-241 Thermal 5.815890e-19 3.721570e-19
Cr- 69 Pu-241 Fast 3.344920e-17 2.140750e-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