Level energy(keV)   Spin & Parity       
       ground state      9/2+                  
       3.13690E+02       1/2-                  
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)
     120.907851062 ± 0.000029430 (amu)  [mass excess = -85836.183 ± 27.415 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     3361.303 ± 27.409 (keV) 
Strong Gamma-rays from Decay of In-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 
        313.6             0.48         IT 
        261.96            7.9          B- 
        657.32            7.1          B- 
        925.57           87.           B- 
         60.1         ~  20.55         B- 
       1041.2             1.13         B- 
       1102.2             0.92         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-           23.1 S 6         
       B-           3.88 M 10        
       IT           3.88 M 10        
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-122 (Z= 50, A=122), MT= 28 (n,np)
     Sn-122 (Z= 50, A=122), MT=104 (n,d)
     Sn-123 (Z= 50, A=123), MT= 32 (n,nd)
     Sn-123 (Z= 50, A=123), MT=105 (n,t)
     Sb-124 (Z= 51, A=124), MT=107 (n,α)
     Sb-125 (Z= 51, 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)
     In-121    U-235   Thermal   2.266750e-05   7.253570e-06 
     In-121    U-235   Fast      4.117380e-05   2.635130e-05 
     In-121    U-235   High      1.073110e-03   6.867900e-04 
     In-121    U-238   Fast      7.191160e-06   4.602340e-06 
     In-121    U-238   High      1.441640e-04   9.226490e-05 
     In-121   Pu-239   Thermal   9.830960e-05   6.291810e-05 
     In-121   Pu-239   Fast      1.719130e-04   1.100240e-04 
     In-121   Pu-239   High      3.842180e-03   2.458990e-03 
     In-121   Pu-241   Thermal   2.223620e-05   1.423110e-05 
     In-121   Pu-241   Fast      8.608060e-05   5.509160e-05 
     In-121m   U-235   Thermal   5.248130e-06   3.358800e-06 
     In-121m   U-235   Fast      8.313950e-06   5.320920e-06 
     In-121m   U-235   High      1.353470e-04   8.662230e-05 
     In-121m   U-238   Fast      1.452060e-06   9.293190e-07 
     In-121m   U-238   High      1.818290e-05   1.163700e-05 
     In-121m  Pu-239   Thermal   2.276130e-05   1.456720e-05 
     In-121m  Pu-239   Fast      3.471330e-05   2.221650e-05 
     In-121m  Pu-239   High      4.845990e-04   3.101430e-04 
     In-121m  Pu-241   Thermal   5.148270e-06   3.294900e-06 
     In-121m  Pu-241   Fast      1.738160e-05   1.112430e-05 
    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)
     In-121    U-235   Thermal   7.440970e-05   4.093760e-05 
     In-121    U-235   Fast      2.400800e-04   1.297150e-04 
     In-121    U-235   High      5.677200e-03   3.063310e-03 
     In-121    U-238   Fast      1.288760e-04   6.947280e-05 
     In-121    U-238   High      2.505340e-03   1.364220e-03 
     In-121   Pu-239   Thermal   2.589000e-04   1.438010e-04 
     In-121   Pu-239   Fast      4.492990e-04   2.475470e-04 
     In-121   Pu-239   High      1.017710e-02   5.520990e-03 
     In-121   Pu-241   Thermal   1.466760e-04   7.949930e-05 
     In-121   Pu-241   Fast      5.491880e-04   2.965150e-04 
     In-121m   U-235   Thermal   5.261620e-05   3.367430e-05 
     In-121m   U-235   Fast      1.276520e-04   8.169750e-05 
     In-121m   U-235   High      4.905220e-03   3.139350e-03 
     In-121m   U-238   Fast      2.432630e-04   1.556880e-04 
     In-121m   U-238   High      5.904350e-03   3.778780e-03 
     In-121m  Pu-239   Thermal   1.128540e-04   7.222700e-05 
     In-121m  Pu-239   Fast      1.686160e-04   1.079140e-04 
     In-121m  Pu-239   High      3.958770e-03   2.533610e-03 
     In-121m  Pu-241   Thermal   1.131320e-04   7.240430e-05 
     In-121m  Pu-241   Fast      3.686060e-04   2.359080e-04 
    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