Level energy(keV)   Spin & Parity       
       ground state      (8-)                  
       4.80000E+00       (4,5)+                
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)
     129.911662054 ± 0.000015288 (amu)  [mass excess = -82286.266 ± 14.241 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     5066.681 ± 14.241 (keV) 
Strong Gamma-rays from Decay of Sb-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 
        330.91           78.           B- 
        793.4           100.           B- 
        839.52          100.           B- 
        182.33           41.           B- 
        793.4            86.           B- 
        839.52          100.           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-           39.5 M 8         
       B-           6.3 M 2          
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Te-130 (Z= 52, A=130), MT=103 (n,p)
     Te-132 (Z= 52, A=132), MT= 32 (n,nd)
     Te-132 (Z= 52, A=132), MT=105 (n,t)
     Cs-137 (Z= 55, A=137), MT=108 (n,2α)

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)
     Sb-130    U-235   Thermal   2.110460e-03   1.350690e-03 
     Sb-130    U-235   Fast      1.502790e-03   9.617810e-04 
     Sb-130    U-235   High      1.169990e-02   3.743980e-03 
     Sb-130    U-238   Fast      8.017320e-04   5.131090e-04 
     Sb-130    U-238   High      7.447140e-03   4.766170e-03 
     Sb-130   Pu-239   Thermal   4.362040e-03   3.489630e-04 
     Sb-130   Pu-239   Fast      4.707180e-03   3.012600e-03 
     Sb-130   Pu-239   High      1.321230e-02   4.227930e-03 
     Sb-130   Pu-241   Thermal   2.065970e-03   1.322220e-03 
     Sb-130   Pu-241   Fast      1.885010e-03   1.206410e-03 
     Sb-130m   U-235   Thermal   3.593480e-03   2.299830e-03 
     Sb-130m   U-235   Fast      2.101020e-03   1.344660e-03 
     Sb-130m   U-235   High      8.790290e-03   5.625790e-03 
     Sb-130m   U-238   Fast      1.120890e-03   7.173660e-04 
     Sb-130m   U-238   High      5.595140e-03   3.580890e-03 
     Sb-130m  Pu-239   Thermal   7.427250e-03   5.941800e-04 
     Sb-130m  Pu-239   Fast      6.581030e-03   2.105930e-03 
     Sb-130m  Pu-239   High      9.926560e-03   6.353000e-03 
     Sb-130m  Pu-241   Thermal   3.517740e-03   2.251350e-03 
     Sb-130m  Pu-241   Fast      2.635390e-03   1.686650e-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)
     Sb-130    U-235   Thermal   9.704660e-03   5.347400e-03 
     Sb-130    U-235   Fast      1.116830e-02   6.043830e-03 
     Sb-130    U-235   High      1.842280e-02   1.048260e-02 
     Sb-130    U-238   Fast      1.286210e-02   6.935050e-03 
     Sb-130    U-238   High      1.999590e-02   1.092070e-02 
     Sb-130   Pu-239   Thermal   1.094810e-02   6.128140e-03 
     Sb-130   Pu-239   Fast      1.266300e-02   6.991770e-03 
     Sb-130   Pu-239   High      1.777750e-02   1.041290e-02 
     Sb-130   Pu-241   Thermal   1.082200e-02   5.886190e-03 
     Sb-130   Pu-241   Fast      1.211290e-02   6.540190e-03 
     Sb-130m   U-235   Thermal   7.819720e-03   5.004620e-03 
     Sb-130m   U-235   Fast      6.777920e-03   4.337870e-03 
     Sb-130m   U-235   High      1.080010e-02   6.912050e-03 
     Sb-130m   U-238   Fast      6.523500e-03   4.175040e-03 
     Sb-130m   U-238   High      1.096750e-02   7.019200e-03 
     Sb-130m  Pu-239   Thermal   1.067450e-02   6.831700e-03 
     Sb-130m  Pu-239   Fast      1.001770e-02   6.411290e-03 
     Sb-130m  Pu-239   High      1.117990e-02   7.155140e-03 
     Sb-130m  Pu-241   Thermal   7.390180e-03   4.729720e-03 
     Sb-130m  Pu-241   Fast      6.528760e-03   4.178410e-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