36-Kr-101



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)
     100.968730 ± 0.000540 (amu)  [mass excess = -29128 ± 503 (keV) ]
 	[These values were derived from systematical trend]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     13684 ± 547 (keV) [derived from systematical trend] 
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0 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-101    U-235   Thermal   4.129510e-13   2.642890e-13 
     Kr-101    U-235   Fast      3.503440e-13   2.242200e-13 
     Kr-101    U-238   Fast      2.241050e-11   1.434270e-11 
     Kr-101    U-238   High      1.241590e-10   7.946170e-11 
     Kr-101   Pu-241   Thermal   5.282300e-13   3.380670e-13 
     Kr-101   Pu-241   Fast      1.426470e-12   9.129410e-13 
    -----------------------------------------------------------
    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-101    U-235   Thermal   4.129510e-13   2.642890e-13 
     Kr-101    U-235   Fast      3.503440e-13   2.242200e-13 
     Kr-101    U-238   Fast      2.241050e-11   1.433740e-11 
     Kr-101    U-238   High      1.241590e-10   7.937560e-11 
     Kr-101   Pu-241   Thermal   5.282300e-13   3.380120e-13 
     Kr-101   Pu-241   Fast      1.426470e-12   9.129410e-13 
    -----------------------------------------------------------
    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