36-Kr-83
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
4.15569E+01 1/2-
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)
82.914127164 ± 0.000000321 (amu) [mass excess = -79990.031 ± 0.300 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-919.402 ± 2.348 (keV)
Strong Gamma-rays from Decay of Kr- 83 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
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9.41 5. IT
32.15 0.06 IT
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*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
IT 1.83 H 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Kr-83.
Figures of cross sections, Kr-83: 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- 82 (Z= 36, A= 82), MT=102 (n,γ)
Kr- 83 (Z= 36, A= 83), MT= 2 (Elastic scattering)
Kr- 83 (Z= 36, A= 83), MT= 4 (Inelastic scattering)
Kr- 84 (Z= 36, A= 84), MT= 16 (n,2n)
Kr- 85 (Z= 36, A= 85), MT= 17 (n,3n)
Rb- 85 (Z= 37, A= 85), MT= 32 (n,nd)
Rb- 85 (Z= 37, A= 85), MT=105 (n,t)
Sr- 86 (Z= 38, A= 86), MT=107 (n,α)
Sr- 87 (Z= 38, A= 87), 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- 83 U-235 Thermal 6.631600e-08 4.244220e-08
Kr- 83 U-235 Fast 4.132330e-08 2.644700e-08
Kr- 83 U-235 High 2.957540e-06 1.892830e-06
Kr- 83 U-238 Fast 1.543940e-09 9.881180e-10
Kr- 83 U-238 High 1.548590e-07 9.910920e-08
Kr- 83 Pu-239 Thermal 1.242160e-06 7.949850e-07
Kr- 83 Pu-239 Fast 5.298980e-07 3.391350e-07
Kr- 83 Pu-239 High 3.475220e-06 2.224140e-06
Kr- 83 Pu-241 Thermal 7.260450e-08 4.646690e-08
Kr- 83 Pu-241 Fast 1.952900e-08 1.249860e-08
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Kr- 83m U-235 Thermal 1.535390e-08 9.826530e-09
Kr- 83m U-235 Fast 8.344130e-09 5.340240e-09
Kr- 83m U-235 High 3.730230e-07 2.387340e-07
Kr- 83m U-238 Fast 3.117560e-10 1.995240e-10
Kr- 83m U-238 High 1.953170e-08 1.250030e-08
Kr- 83m Pu-239 Thermal 2.875940e-07 1.840610e-07
Kr- 83m Pu-239 Fast 1.069990e-07 6.847930e-08
Kr- 83m Pu-239 High 4.383160e-07 2.805220e-07
Kr- 83m Pu-241 Thermal 1.680990e-08 1.075830e-08
Kr- 83m Pu-241 Fast 3.943350e-09 2.523750e-09
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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- 83 U-235 Thermal 5.395910e-03 4.320250e-05
Kr- 83 U-235 Fast 5.755660e-03 5.844940e-05
Kr- 83 U-235 High 1.102710e-02 4.407610e-04
Kr- 83 U-238 Fast 3.968990e-03 5.639240e-05
Kr- 83 U-238 High 6.691630e-03 1.876290e-04
Kr- 83 Pu-239 Thermal 2.967380e-03 1.483680e-05
Kr- 83 Pu-239 Fast 3.155240e-03 2.208630e-05
Kr- 83 Pu-239 High 4.739610e-03 5.207110e-04
Kr- 83 Pu-241 Thermal 2.015620e-03 2.822300e-05
Kr- 83 Pu-241 Fast 2.033780e-03 2.848330e-05
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Kr- 83m U-235 Thermal 5.394760e-03 6.285750e-05
Kr- 83m U-235 Fast 5.754470e-03 1.158070e-04
Kr- 83m U-235 High 1.102190e-02 6.603940e-04
Kr- 83m U-238 Fast 3.968190e-03 1.112580e-04
Kr- 83m U-238 High 6.690130e-03 4.007850e-04
Kr- 83m Pu-239 Thermal 2.965540e-03 2.966530e-05
Kr- 83m Pu-239 Fast 3.154080e-03 4.416430e-05
Kr- 83m Pu-239 High 4.735180e-03 1.087890e-03
Kr- 83m Pu-241 Thermal 2.015150e-03 5.640980e-05
Kr- 83m Pu-241 Fast 2.033360e-03 5.696510e-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