36-Kr-84



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       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)
     83.91149772816 ± 0.00000000442 (amu)  [mass excess = -82439.33541 ± 0.00412 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2680.375 ± 2.194 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Kr-84.
     Figures of cross sections, Kr-84:  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- 83 (Z= 36, A= 83), MT=102 (n,γ)
     Kr- 84 (Z= 36, A= 84), MT=  2 (Elastic scattering)
     Kr- 84 (Z= 36, A= 84), MT=  4 (Inelastic scattering)
     Kr- 85 (Z= 36, A= 85), MT= 16 (n,2n)
     Kr- 86 (Z= 36, A= 86), MT= 17 (n,3n)
     Rb- 85 (Z= 37, A= 85), MT= 28 (n,np)
     Rb- 85 (Z= 37, A= 85), MT=104 (n,d)
     Rb- 86 (Z= 37, A= 86), MT= 32 (n,nd)
     Rb- 86 (Z= 37, A= 86), MT=105 (n,t)
     Sr- 86 (Z= 38, A= 86), MT=106 (n,3He)
     Sr- 87 (Z= 38, A= 87), MT=107 (n,α)
     Sr- 88 (Z= 38, A= 88), 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- 84    U-235   Thermal   3.244830e-06   2.076690e-06 
     Kr- 84    U-235   Fast      2.015840e-06   1.290140e-06 
     Kr- 84    U-235   High      3.864290e-05   2.473150e-05 
     Kr- 84    U-238   Fast      9.343480e-08   5.979830e-08 
     Kr- 84    U-238   High      3.764100e-06   2.409020e-06 
     Kr- 84   Pu-239   Thermal   2.607590e-05   1.668860e-05 
     Kr- 84   Pu-239   Fast      1.189810e-05   7.614770e-06 
     Kr- 84   Pu-239   High      4.456890e-05   2.852410e-05 
     Kr- 84   Pu-241   Thermal   2.340380e-06   1.497840e-06 
     Kr- 84   Pu-241   Fast      7.534330e-07   4.821970e-07 
    -----------------------------------------------------------
    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- 84    U-235   Thermal   9.895240e-03   1.424240e-04 
     Kr- 84    U-235   Fast      1.028700e-02   1.456520e-04 
     Kr- 84    U-235   High      1.510960e-02   1.659670e-03 
     Kr- 84    U-238   Fast      8.253690e-03   1.156000e-04 
     Kr- 84    U-238   High      1.124830e-02   3.148350e-04 
     Kr- 84   Pu-239   Thermal   4.802970e-03   4.803300e-05 
     Kr- 84   Pu-239   Fast      4.986460e-03   4.986720e-05 
     Kr- 84   Pu-239   High      7.980200e-03   1.276010e-03 
     Kr- 84   Pu-241   Thermal   3.513930e-03   7.026500e-05 
     Kr- 84   Pu-241   Fast      3.565810e-03   5.000410e-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