53-I-145



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)
     144.956050 ± 0.000540 (amu)  [mass excess = -40939 ± 503 (keV) ]
 	[These values were derived from systematical trend]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     10554 ± 503 (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)
    -----------------------------------------------------------
      I-145    U-235   Thermal   8.272740e-12   5.294550e-12 
      I-145    U-235   Fast      3.581580e-09   2.292210e-09 
      I-145    U-235   High      5.936330e-10   3.799250e-10 
      I-145    U-238   Fast      1.170410e-07   7.490630e-08 
      I-145    U-238   High      1.170030e-07   7.488210e-08 
      I-145   Pu-239   Thermal   2.724600e-11   1.743750e-11 
      I-145   Pu-239   Fast      1.701290e-11   1.088830e-11 
      I-145   Pu-239   High      1.459970e-10   9.343780e-11 
      I-145   Pu-241   Thermal   5.181880e-09   3.316410e-09 
      I-145   Pu-241   Fast      4.663710e-09   2.984780e-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)
    -----------------------------------------------------------
      I-145    U-235   Thermal   8.272740e-12   5.294550e-12 
      I-145    U-235   Fast      3.581690e-09   2.292280e-09 
      I-145    U-235   High      5.936330e-10   3.793620e-10 
      I-145    U-238   Fast      1.170470e-07   7.488280e-08 
      I-145    U-238   High      1.170270e-07   7.481610e-08 
      I-145   Pu-239   Thermal   2.724600e-11   1.743750e-11 
      I-145   Pu-239   Fast      1.701290e-11   1.088830e-11 
      I-145   Pu-239   High      1.459970e-10   9.337730e-11 
      I-145   Pu-241   Thermal   5.182060e-09   3.315980e-09 
      I-145   Pu-241   Fast      4.663920e-09   2.984920e-09 
    -----------------------------------------------------------
    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