53-I-143



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state                            
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)
     142.945650 ± 0.000320 (amu)  [mass excess = -50627 ± 298 (keV) ]
 	[These values were derived from systematical trend]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     9576 ± 298 (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-143    U-235   Thermal   1.856130e-07   1.187920e-07 
      I-143    U-235   Fast      2.677510e-07   1.713610e-07 
      I-143    U-235   High      7.866520e-07   5.034580e-07 
      I-143    U-238   Fast      7.473690e-05   4.783160e-05 
      I-143    U-238   High      5.302600e-06   3.393670e-06 
      I-143   Pu-239   Thermal   1.150940e-07   7.366060e-08 
      I-143   Pu-239   Fast      1.129730e-07   7.230270e-08 
      I-143   Pu-239   High      2.356180e-08   1.507960e-08 
      I-143   Pu-241   Thermal   6.370860e-07   4.077350e-07 
      I-143   Pu-241   Fast      7.149410e-07   4.575630e-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)
    -----------------------------------------------------------
      I-143    U-235   Thermal   1.856170e-07   1.187950e-07 
      I-143    U-235   Fast      2.677590e-07   1.713660e-07 
      I-143    U-235   High      7.869830e-07   5.029230e-07 
      I-143    U-238   Fast      7.482240e-05   4.786880e-05 
      I-143    U-238   High      5.303670e-06   3.390670e-06 
      I-143   Pu-239   Thermal   1.151020e-07   7.366530e-08 
      I-143   Pu-239   Fast      1.129810e-07   7.230800e-08 
      I-143   Pu-239   High      2.356180e-08   1.506980e-08 
      I-143   Pu-241   Thermal   6.371090e-07   4.076840e-07 
      I-143   Pu-241   Fast      7.149740e-07   4.575830e-07 
    -----------------------------------------------------------
    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