36-Kr-86
Spin
Level energy(keV) Spin & Parity
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ground state 0+
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer
Chinese Physics C36 p. 1603-2014, December 2012)
85.91061062693 ± 0.00000000407 (amu) [mass excess = -83265.66488 ± 0.00379 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-518.655 ± 0.199 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Kr-86.
Figures of cross sections, Kr-86: type-1: type-2: type-3.
type-1: total, elastic and inelastic scattering, capture and fision cross sections
type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
type-3: threshold reaction cross sections
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Kr- 85 (Z= 36, A= 85), MT=102 (n,γ)
Kr- 86 (Z= 36, A= 86), MT= 2 (Elastic scattering)
Kr- 86 (Z= 36, A= 86), MT= 4 (Inelastic scattering)
Rb- 86 (Z= 37, A= 86), MT=103 (n,p)
Rb- 87 (Z= 37, A= 87), MT= 28 (n,np)
Rb- 87 (Z= 37, A= 87), MT=104 (n,d)
Sr- 88 (Z= 38, A= 88), MT=106 (n,3He)
Sr- 89 (Z= 38, A= 89), MT=107 (n,α)
Sr- 90 (Z= 38, A= 90), MT= 22 (n,nα)
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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Kr- 86 U-235 Thermal 8.709030e-04 6.967230e-05
Kr- 86 U-235 Fast 1.538840e-03 4.924270e-04
Kr- 86 U-235 High 1.292500e-03 8.272010e-04
Kr- 86 U-238 Fast 3.856430e-05 2.468120e-05
Kr- 86 U-238 High 2.926280e-04 1.872820e-04
Kr- 86 Pu-239 Thermal 7.052590e-04 1.622090e-04
Kr- 86 Pu-239 Fast 7.556680e-04 4.836270e-04
Kr- 86 Pu-239 High 1.241310e-03 7.944350e-04
Kr- 86 Pu-241 Thermal 2.446500e-04 1.565750e-04
Kr- 86 Pu-241 Fast 1.264350e-04 8.091840e-05
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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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Kr- 86 U-235 Thermal 1.955710e-02 1.350170e-04
Kr- 86 U-235 Fast 1.941160e-02 2.026570e-04
Kr- 86 U-235 High 1.828060e-02 4.204190e-03
Kr- 86 U-238 Fast 1.288500e-02 1.520900e-04
Kr- 86 U-238 High 1.566550e-02 4.421540e-04
Kr- 86 Pu-239 Thermal 7.659230e-03 3.830990e-05
Kr- 86 Pu-239 Fast 7.887550e-03 7.892920e-05
Kr- 86 Pu-239 High 1.130870e-02 1.244470e-03
Kr- 86 Pu-241 Thermal 5.942220e-03 1.189200e-04
Kr- 86 Pu-241 Fast 5.979650e-03 8.496440e-05
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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