Level energy(keV)   Spin & Parity       
       ground state      (3/2+)                
       3.34270E+02       11/2-                 
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)
     132.910968766 ± 0.000003873 (amu)  [mass excess = -82932.060 ± 3.608 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     2954.511 ± 5.897 (keV) 
Strong Gamma-rays from Decay of Te-133 (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 
        312.08           62.4          B- 
        407.63           27.08         B- 
       1333.21           10.67         B- 
        334.27            7.17         IT 
        647.51           19.4          B- 
        863.96           15.64         B- 
        912.67           55.27         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-           55.4 M 4         
       B-           12.5 M 3         
       IT           55.4 M 4         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Te-132 (Z= 52, A=132), MT=102 (n,γ)
     I -135 (Z= 53, A=135), MT= 32 (n,nd)
     I -135 (Z= 53, A=135), MT=105 (n,t)
     Xe-135 (Z= 54, A=135), MT=106 (n,3He)
     Xe-136 (Z= 54, A=136), MT=107 (n,α)
     Cs-137 (Z= 55, A=137), MT=112 (n,pα)

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)
     Te-133    U-235   Thermal   1.209470e-02   7.256880e-04 
     Te-133    U-235   Fast      1.225550e-02   3.921750e-03 
     Te-133    U-235   High      5.344570e-03   3.420530e-03 
     Te-133    U-238   Fast      7.267300e-03   4.651070e-03 
     Te-133    U-238   High      5.555550e-03   3.555550e-03 
     Te-133   Pu-239   Thermal   1.364290e-02   1.500730e-03 
     Te-133   Pu-239   Fast      1.151670e-02   3.685360e-03 
     Te-133   Pu-239   High      3.828870e-03   2.450480e-03 
     Te-133   Pu-241   Thermal   1.180130e-02   3.776430e-03 
     Te-133   Pu-241   Fast      9.792570e-03   6.267250e-03 
     Te-133m   U-235   Thermal   2.918420e-02   1.751050e-03 
     Te-133m   U-235   Fast      3.434320e-02   3.777760e-03 
     Te-133m   U-235   High      2.451340e-02   7.844270e-03 
     Te-133m   U-238   Fast      2.036500e-02   6.516800e-03 
     Te-133m   U-238   High      2.548100e-02   8.153930e-03 
     Te-133m  Pu-239   Thermal   3.292000e-02   1.975200e-03 
     Te-133m  Pu-239   Fast      3.227310e-02   3.550030e-03 
     Te-133m  Pu-239   High      1.756150e-02   5.619670e-03 
     Te-133m  Pu-241   Thermal   2.847630e-02   9.112400e-03 
     Te-133m  Pu-241   Fast      2.744150e-02   8.781290e-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)
     Te-133    U-235   Thermal   3.788900e-02   6.737330e-03 
     Te-133    U-235   Fast      3.269290e-02   9.273810e-03 
     Te-133    U-235   High      1.593010e-02   5.065890e-03 
     Te-133    U-238   Fast      4.358710e-02   1.238360e-02 
     Te-133    U-238   High      3.102940e-02   8.755770e-03 
     Te-133   Pu-239   Thermal   2.993870e-02   5.092670e-03 
     Te-133   Pu-239   Fast      2.784890e-02   5.820970e-03 
     Te-133   Pu-239   High      1.000190e-02   4.104460e-03 
     Te-133   Pu-241   Thermal   3.983710e-02   1.274170e-02 
     Te-133   Pu-241   Fast      3.563600e-02   9.488110e-03 
     Te-133m   U-235   Thermal   3.333100e-02   6.067110e-03 
     Te-133m   U-235   Fast      3.722120e-02   5.336850e-03 
     Te-133m   U-235   High      2.575980e-02   6.556990e-03 
     Te-133m   U-238   Fast      2.696920e-02   1.256780e-02 
     Te-133m   U-238   High      2.970170e-02   1.014320e-02 
     Te-133m  Pu-239   Thermal   3.501380e-02   3.351530e-03 
     Te-133m  Pu-239   Fast      3.439700e-02   3.772680e-03 
     Te-133m  Pu-239   High      1.816970e-02   4.457830e-03 
     Te-133m  Pu-241   Thermal   3.310320e-02   1.903070e-02 
     Te-133m  Pu-241   Fast      3.166310e-02   1.056650e-02 
    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