36-Kr-86



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)
     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)
    -----------------------------------------------------------
     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 
    -----------------------------------------------------------
    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- 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 
    -----------------------------------------------------------
    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