Level energy(keV)   Spin & Parity       
       ground state      9/2+                  
       3.04870E+02       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)
     84.912527262 ± 0.000002147 (amu)  [mass excess = -81480.330 ± 2.000 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     687.000 ± 2.000 (keV) 
Strong Gamma-rays from Decay of Kr- 85 (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 
        151.18          2.E-06         B- 
        362.81          2.E-06         B- 
        514.00            0.43         B- 
        304.87           14.02         IT 
        129.81            0.3          B- 
        151.19           74.98         B- 
        451.0             0.01         B- 
     *: 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 
       B-           4.480 H 8        
       B-           10.756 Y 18      
       IT           4.480 H 8        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Kr-85.
     Figures of cross sections, Kr-85:  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- 84 (Z= 36, A= 84), MT=102 (n,γ)
     Kr- 85 (Z= 36, A= 85), MT=  2 (Elastic scattering)
     Kr- 85 (Z= 36, A= 85), MT=  4 (Inelastic scattering)
     Kr- 86 (Z= 36, A= 86), MT= 16 (n,2n)
     Rb- 85 (Z= 37, A= 85), MT=103 (n,p)
     Rb- 86 (Z= 37, A= 86), MT= 28 (n,np)
     Rb- 86 (Z= 37, A= 86), MT=104 (n,d)
     Rb- 87 (Z= 37, A= 87), MT= 32 (n,nd)
     Rb- 87 (Z= 37, A= 87), MT=105 (n,t)
     Sr- 87 (Z= 38, A= 87), MT=106 (n,3He)
     Sr- 88 (Z= 38, A= 88), MT=107 (n,α)
     Sr- 89 (Z= 38, A= 89), 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- 85    U-235   Thermal   2.547730e-04   4.076370e-05 
     Kr- 85    U-235   Fast      3.095300e-05   1.980990e-05 
     Kr- 85    U-235   High      2.740750e-04   1.754080e-04 
     Kr- 85    U-238   Fast      1.995880e-06   1.277370e-06 
     Kr- 85    U-238   High      3.234060e-05   2.069800e-05 
     Kr- 85   Pu-239   Thermal   1.005260e-04   6.433660e-05 
     Kr- 85   Pu-239   Fast      9.493250e-05   6.075680e-05 
     Kr- 85   Pu-239   High      2.925810e-04   1.872520e-04 
     Kr- 85   Pu-241   Thermal   2.384420e-05   1.526030e-05 
     Kr- 85   Pu-241   Fast      1.023420e-05   6.549900e-06 
     Kr- 85m   U-235   Thermal   5.898700e-05   9.437910e-06 
     Kr- 85m   U-235   Fast      6.250130e-06   4.000080e-06 
     Kr- 85m   U-235   High      3.456800e-05   2.212350e-05 
     Kr- 85m   U-238   Fast      4.030140e-07   2.579290e-07 
     Kr- 85m   U-238   High      4.079000e-06   2.610560e-06 
     Kr- 85m  Pu-239   Thermal   2.327450e-05   1.489570e-05 
     Kr- 85m  Pu-239   Fast      1.916910e-05   1.226820e-05 
     Kr- 85m  Pu-239   High      3.690220e-05   2.361740e-05 
     Kr- 85m  Pu-241   Thermal   5.520570e-06   3.533170e-06 
     Kr- 85m  Pu-241   Fast      2.066530e-06   1.322580e-06 
    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- 85    U-235   Thermal   3.061320e-03   2.276640e-04 
     Kr- 85    U-235   Fast      2.960730e-03   2.182300e-04 
     Kr- 85    U-235   High      3.815270e-03   3.422730e-04 
     Kr- 85    U-238   Fast      1.621570e-03   1.386380e-04 
     Kr- 85    U-238   High      2.207990e-03   1.770740e-04 
     Kr- 85   Pu-239   Thermal   1.315640e-03   8.872300e-05 
     Kr- 85   Pu-239   Fast      1.376330e-03   1.001120e-04 
     Kr- 85   Pu-239   High      2.313060e-03   3.774380e-04 
     Kr- 85   Pu-241   Thermal   8.956160e-04   6.849230e-05 
     Kr- 85   Pu-241   Fast      9.714650e-04   8.928970e-05 
     Kr- 85m   U-235   Thermal   1.300560e-02   1.082060e-04 
     Kr- 85m   U-235   Fast      1.357620e-02   1.929440e-04 
     Kr- 85m   U-235   High      1.640970e-02   6.558670e-04 
     Kr- 85m   U-238   Fast      7.504870e-03   1.670230e-04 
     Kr- 85m   U-238   High      1.008160e-02   2.077610e-04 
     Kr- 85m  Pu-239   Thermal   5.630840e-03   4.044600e-05 
     Kr- 85m  Pu-239   Fast      5.937980e-03   8.359910e-05 
     Kr- 85m  Pu-239   High      9.362920e-03   2.620820e-04 
     Kr- 85m  Pu-241   Thermal   4.039710e-03   1.131560e-04 
     Kr- 85m  Pu-241   Fast      4.454220e-03   2.673190e-04 
    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