Level energy(keV)   Spin & Parity       
       ground state      (1-)                  
       6.40000E+02       (6-)                  
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)
     135.914604412 ± 0.000015238 (amu)  [mass excess = -79545.478 ± 14.195 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     6883.674 ± 14.195 (keV) 
Strong Gamma-rays from Decay of I-136 (Compiled from ENSDF as of March 2011)
  [ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
   γ-ray energy(keV)  Intensity(%)  Decay mode 
        197.32           78.3          B- 
        381.36           99.8          B- 
       1313.02          100.           B- 
       1313.02           66.7          B- 
       1321.08           24.81         B- 
       2289.6            10.41         B- 
        240.5          *  3.4          B- 
       1686.1          *  4.6          B- 
       1689.0          *  3.9          B- 
     *: relative, ~ approximate, ? calculated or estimatted 
     >: greater than or equal to, <: less than or equal to  
  [ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
     Decay mode     Half-life 
       B-           46.9 S 10        
       B-           46.9 S 10        
       B-           83.4 S 10        
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     I -135 (Z= 53, A=135), MT=102 (n,γ)
     Xe-136 (Z= 54, A=136), MT=103 (n,p)
     Cs-137 (Z= 55, A=137), MT=111 (n,2p)

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-136    U-235   Thermal   7.674450e-03   6.139570e-04 
      I-136    U-235   Fast      8.830380e-03   2.825720e-03 
      I-136    U-235   High      4.440380e-03   1.420920e-03 
      I-136    U-238   Fast      7.168060e-03   2.293780e-03 
      I-136    U-238   High      5.736280e-03   1.835610e-03 
      I-136   Pu-239   Thermal   8.644810e-03   2.766330e-03 
      I-136   Pu-239   Fast      8.582800e-03   2.746500e-03 
      I-136   Pu-239   High      3.793000e-03   1.213760e-03 
      I-136   Pu-241   Thermal   1.204670e-02   3.854970e-03 
      I-136   Pu-241   Fast      9.106810e-03   2.914190e-03 
      I-136m   U-235   Thermal   1.799260e-02   1.079560e-03 
      I-136m   U-235   Fast      2.411880e-02   5.547310e-03 
      I-136m   U-235   High      2.009210e-02   6.429500e-03 
      I-136m   U-238   Fast      1.957840e-02   6.265090e-03 
      I-136m   U-238   High      2.595590e-02   8.305880e-03 
      I-136m  Pu-239   Thermal   2.026760e-02   1.621410e-03 
      I-136m  Pu-239   Fast      2.344260e-02   7.501640e-03 
      I-136m  Pu-239   High      1.716280e-02   5.492100e-03 
      I-136m  Pu-241   Thermal   2.824340e-02   9.037870e-03 
      I-136m  Pu-241   Fast      2.487380e-02   7.959620e-03 
    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-136    U-235   Thermal   2.091740e-02   1.255370e-03 
      I-136    U-235   Fast      1.900430e-02   3.045040e-03 
      I-136    U-235   High      8.001630e-03   1.836580e-03 
      I-136    U-238   Fast      4.395260e-02   4.818330e-03 
      I-136    U-238   High      2.001960e-02   3.193230e-03 
      I-136   Pu-239   Thermal   1.367290e-02   3.144330e-03 
      I-136   Pu-239   Fast      1.528560e-02   3.514990e-03 
      I-136   Pu-239   High      5.852760e-03   1.344720e-03 
      I-136   Pu-241   Thermal   2.892030e-02   6.645020e-03 
      I-136   Pu-241   Fast      2.815270e-02   4.503520e-03 
      I-136m   U-235   Thermal   1.811440e-02   1.088860e-03 
      I-136m   U-235   Fast      2.416230e-02   3.874200e-03 
      I-136m   U-235   High      2.011370e-02   4.619360e-03 
      I-136m   U-238   Fast      2.001020e-02   4.600340e-03 
      I-136m   U-238   High      2.609770e-02   5.995920e-03 
      I-136m  Pu-239   Thermal   2.030260e-02   1.218330e-03 
      I-136m  Pu-239   Fast      2.347380e-02   5.399730e-03 
      I-136m  Pu-239   High      1.717050e-02   3.946660e-03 
      I-136m  Pu-241   Thermal   2.838230e-02   6.526760e-03 
      I-136m  Pu-241   Fast      2.502180e-02   5.759260e-03 
    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