Level energy(keV)   Spin & Parity       
       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 
          9.41            5.           IT 
         32.15            0.06         IT 
     *: 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)
     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 
     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 
    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)
     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 
     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 
    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