Level energy(keV)   Spin & Parity       
       ground state      1+                    
       4.00000E+01       5+                    
       2.90000E+02       (8-)                  
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)
     121.910280738 ± 0.000053739 (amu)  [mass excess = -83572.954 ± 50.058 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     6368.591 ± 50.000 (keV) 
Strong Gamma-rays from Decay of In-122 (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 
       1013.12            2.67         B- 
       1140.28           29.           B- 
       2759.13            3.07         B- 
        103.74           81.           B- 
       1001.58           98.4          B- 
       1140.55          100.           B- 
       1001.58           50.69         B- 
       1140.55           98.04         B- 
       1190.58           20.49         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-           10.3 S 6         
       B-           10.8 S 4         
       B-           1.5 S 3          
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-122 (Z= 50, A=122), MT=103 (n,p)
     Sn-123 (Z= 50, A=123), MT= 28 (n,np)
     Sn-123 (Z= 50, A=123), MT=104 (n,d)
     Sn-124 (Z= 50, A=124), MT=105 (n,t)
     Sb-125 (Z= 51, A=125), MT=107 (n,α)
     Sb-126 (Z= 51, A=126), 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-122    U-235   Thermal   6.249910e-06   3.999940e-06 
     In-122    U-235   Fast      2.398100e-05   1.534780e-05 
     In-122    U-235   High      4.472440e-04   2.862360e-04 
     In-122    U-238   Fast      8.512870e-06   5.448220e-06 
     In-122    U-238   High      9.072300e-05   5.806260e-05 
     In-122   Pu-239   Thermal   5.475150e-05   3.504090e-05 
     In-122   Pu-239   Fast      7.723900e-05   4.943300e-05 
     In-122   Pu-239   High      1.013070e-03   6.483630e-04 
     In-122   Pu-241   Thermal   1.942510e-05   1.243210e-05 
     In-122   Pu-241   Fast      6.164880e-05   3.945530e-05 
     In-122m   U-235   Thermal   2.721680e-05   1.319900e-05 
     In-122m   U-235   Fast      1.194030e-04   5.818970e-05 
     In-122m   U-235   High      3.279800e-03   1.690710e-03 
     In-122m   U-238   Fast      4.238620e-05   2.065640e-05 
     In-122m   U-238   High      7.157040e-04   3.534160e-04 
     In-122m  Pu-239   Thermal   2.384290e-04   1.156280e-04 
     In-122m  Pu-239   Fast      3.845780e-04   1.874200e-04 
     In-122m  Pu-239   High      7.429170e-03   3.829660e-03 
     In-122m  Pu-241   Thermal   8.459170e-05   4.102350e-05 
     In-122m  Pu-241   Fast      3.069540e-04   1.495910e-04 
    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-122    U-235   Thermal   1.320900e-04   8.453790e-05 
     In-122    U-235   Fast      3.088860e-04   1.064290e-04 
     In-122    U-235   High      8.773310e-03   2.014910e-03 
     In-122    U-238   Fast      3.806810e-04   8.920780e-05 
     In-122    U-238   High      7.989910e-03   1.861110e-03 
     In-122   Pu-239   Thermal   2.286940e-04   1.249360e-04 
     In-122   Pu-239   Fast      3.373410e-04   1.869650e-04 
     In-122   Pu-239   High      7.691580e-03   3.458970e-03 
     In-122   Pu-241   Thermal   1.965130e-04   9.515480e-05 
     In-122   Pu-241   Fast      7.105720e-04   3.439240e-04 
     In-122m   U-235   Thermal   2.721680e-05   1.533560e-05 
     In-122m   U-235   Fast      1.194030e-04   6.744850e-05 
     In-122m   U-235   High      3.279800e-03   2.095970e-03 
     In-122m   U-238   Fast      4.238620e-05   2.391240e-05 
     In-122m   U-238   High      7.157040e-04   4.059940e-04 
     In-122m  Pu-239   Thermal   2.384290e-04   1.342490e-04 
     In-122m  Pu-239   Fast      3.845780e-04   2.170200e-04 
     In-122m  Pu-239   High      7.429170e-03   4.751580e-03 
     In-122m  Pu-241   Thermal   8.459170e-05   4.762250e-05 
     In-122m  Pu-241   Fast      3.069540e-04   1.732720e-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