Level energy(keV)   Spin & Parity       
       ground state      3/2+                  
       6.29000E+00       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)
     120.904242554 ± 0.000001033 (amu)  [mass excess = -89197.486 ± 0.963 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     401.089 ± 2.900 (keV) 
Strong Gamma-rays from Decay of Sn-121 (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 
         37.15            1.85         B- 
          6.29            --           IT 
     *: 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-           43.9 Y 5         
       B-           27.03 H 4        
       IT           43.9 Y 5         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-120 (Z= 50, A=120), MT=102 (n,γ)
     Sn-122 (Z= 50, A=122), MT= 16 (n,2n)
     Sn-123 (Z= 50, A=123), MT= 17 (n,3n)
     Sb-121 (Z= 51, A=121), MT=103 (n,p)
     Sb-123 (Z= 51, A=123), MT=105 (n,t)
     Sb-124 (Z= 51, A=124), MT= 33 (n,nt)
     Te-123 (Z= 52, A=123), MT=106 (n,3He)
     Te-124 (Z= 52, A=124), MT=107 (n,α)
     Te-125 (Z= 52, A=125), MT= 22 (n,nα)

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-121    U-235   Thermal   2.723980e-06   1.743350e-06 
     Sn-121    U-235   Fast      8.193260e-07   5.243690e-07 
     Sn-121    U-235   High      2.416230e-05   1.546390e-05 
     Sn-121    U-238   Fast      2.480930e-08   1.587800e-08 
     Sn-121    U-238   High      6.986110e-07   4.471100e-07 
     Sn-121   Pu-239   Thermal   5.372350e-06   3.438300e-06 
     Sn-121   Pu-239   Fast      1.091320e-05   6.984460e-06 
     Sn-121   Pu-239   High      2.974440e-04   1.903640e-04 
     Sn-121   Pu-241   Thermal   2.609250e-07   1.669920e-07 
     Sn-121   Pu-241   Fast      1.274050e-06   8.153930e-07 
     Sn-121m   U-235   Thermal   1.128890e-06   7.224890e-07 
     Sn-121m   U-235   Fast      2.923780e-07   1.871220e-07 
     Sn-121m   U-235   High      5.268040e-06   3.371550e-06 
     Sn-121m   U-238   Fast      8.853260e-09   5.666080e-09 
     Sn-121m   U-238   High      1.523160e-07   9.748220e-08 
     Sn-121m  Pu-239   Thermal   2.226450e-06   1.424930e-06 
     Sn-121m  Pu-239   Fast      3.894400e-06   2.492420e-06 
     Sn-121m  Pu-239   High      6.485080e-05   4.150460e-05 
     Sn-121m  Pu-241   Thermal   1.081350e-07   6.920610e-08 
     Sn-121m  Pu-241   Fast      4.546480e-07   2.909750e-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)
     Sn-121    U-235   Thermal   1.281610e-04   8.190990e-05 
     Sn-121    U-235   Fast      3.613310e-04   2.312520e-04 
     Sn-121    U-235   High      1.041190e-02   6.663670e-03 
     Sn-121    U-238   Fast      3.660760e-04   2.342880e-04 
     Sn-121    U-238   High      8.277910e-03   5.297860e-03 
     Sn-121   Pu-239   Thermal   3.711210e-04   2.375170e-04 
     Sn-121   Pu-239   Fast      6.187560e-04   3.960040e-04 
     Sn-121   Pu-239   High      1.418540e-02   9.078680e-03 
     Sn-121   Pu-241   Thermal   2.551810e-04   1.633160e-04 
     Sn-121   Pu-241   Fast      9.014650e-04   5.769380e-04 
     Sn-121m   U-235   Thermal   9.313950e-06   5.325270e-06 
     Sn-121m   U-235   Fast      2.670120e-05   1.449210e-05 
     Sn-121m   U-235   High      6.297600e-04   3.394770e-04 
     Sn-121m   U-238   Fast      1.418520e-05   7.651200e-06 
     Sn-121m   U-238   High      2.757390e-04   1.494310e-04 
     Sn-121m  Pu-239   Thermal   3.070540e-05   1.738180e-05 
     Sn-121m  Pu-239   Fast      5.331730e-05   2.989030e-05 
     Sn-121m  Pu-239   High      1.184340e-03   6.493560e-04 
     Sn-121m  Pu-241   Thermal   1.624250e-05   8.857080e-06 
     Sn-121m  Pu-241   Fast      6.086530e-05   3.298630e-05 
    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