Level energy(keV)   Spin & Parity       
       ground state      0+                    
       1.94688E+03       (7-)                  
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)
     129.913973830 ± 0.000002282 (amu)  [mass excess = -80132.861 ± 2.126 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     2153.406 ± 14.113 (keV) 
Strong Gamma-rays from Decay of Sn-130 (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 
         84.67            9.54         B- 
        144.91           22.66         B- 
        733.4            23.           B- 
         70.01           34.1          B- 
        192.42           67.           B- 
        780.44           56.43         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-           1.7 M 1          
       B-           3.72 M 7         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Te-132 (Z= 52, A=132), MT=106 (n,3He)

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)
     Sn-130    U-235   Thermal   3.237660e-03   2.072100e-03 
     Sn-130    U-235   Fast      3.537410e-03   2.263940e-03 
     Sn-130    U-235   High      1.485650e-03   9.508170e-04 
     Sn-130    U-238   Fast      4.414600e-03   2.825340e-03 
     Sn-130    U-238   High      2.772260e-03   1.774250e-03 
     Sn-130   Pu-239   Thermal   2.808820e-03   1.797640e-03 
     Sn-130   Pu-239   Fast      2.912430e-03   1.863960e-03 
     Sn-130   Pu-239   High      1.008860e-03   6.456730e-04 
     Sn-130   Pu-241   Thermal   3.733450e-03   2.389400e-03 
     Sn-130   Pu-241   Fast      3.743240e-03   2.395670e-03 
     Sn-130m   U-235   Thermal   7.590640e-03   4.858010e-03 
     Sn-130m   U-235   Fast      9.661880e-03   6.183610e-03 
     Sn-130m   U-235   High      6.722370e-03   4.302320e-03 
     Sn-130m   U-238   Fast      1.205780e-02   7.716980e-03 
     Sn-130m   U-238   High      1.254410e-02   8.028230e-03 
     Sn-130m  Pu-239   Thermal   6.585220e-03   4.214540e-03 
     Sn-130m  Pu-239   Fast      7.954860e-03   5.091120e-03 
     Sn-130m  Pu-239   High      4.564970e-03   2.921580e-03 
     Sn-130m  Pu-241   Thermal   8.753000e-03   5.601910e-03 
     Sn-130m  Pu-241   Fast      1.022410e-02   6.543410e-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)
     Sn-130    U-235   Thermal   4.226240e-03   2.531220e-03 
     Sn-130    U-235   Fast      4.676900e-03   2.712320e-03 
     Sn-130    U-235   High      2.009790e-03   1.155210e-03 
     Sn-130    U-238   Fast      5.402610e-03   3.196800e-03 
     Sn-130    U-238   High      5.372350e-03   2.926320e-03 
     Sn-130   Pu-239   Thermal   3.247280e-03   1.958910e-03 
     Sn-130   Pu-239   Fast      3.436640e-03   2.058420e-03 
     Sn-130   Pu-239   High      1.253370e-03   7.377990e-04 
     Sn-130   Pu-241   Thermal   3.872440e-03   2.440310e-03 
     Sn-130   Pu-241   Fast      3.893370e-03   2.453430e-03 
     Sn-130m   U-235   Thermal   7.594200e-03   4.860290e-03 
     Sn-130m   U-235   Fast      9.665560e-03   6.185950e-03 
     Sn-130m   U-235   High      6.722930e-03   4.302670e-03 
     Sn-130m   U-238   Fast      1.206040e-02   7.718670e-03 
     Sn-130m   U-238   High      1.254870e-02   8.031190e-03 
     Sn-130m  Pu-239   Thermal   6.586080e-03   4.215090e-03 
     Sn-130m  Pu-239   Fast      7.955780e-03   5.091700e-03 
     Sn-130m  Pu-239   High      4.565180e-03   2.921710e-03 
     Sn-130m  Pu-241   Thermal   8.756040e-03   5.603870e-03 
     Sn-130m  Pu-241   Fast      1.022790e-02   6.545830e-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