Level energy(keV)   Spin & Parity       
       ground state      (9/2)+                
       3.27210E+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)
     122.910433718 ± 0.000021285 (amu)  [mass excess = -83430.454 ± 19.827 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     4385.936 ± 19.839 (keV) 
Strong Gamma-rays from Decay of In-123 (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 
        125.76        ~*40000.         B- 
       1170.           *100.           B- 
       3234.           *122.           B- 
        618.8             2.5          B- 
       1019.7            30.72         B- 
       1130.5            60.48         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-           47.4 S 4         
       B-           6.17 S 5         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-123 (Z= 50, A=123), MT=103 (n,p)
     Sn-124 (Z= 50, A=124), MT= 28 (n,np)
     Sn-124 (Z= 50, A=124), MT=104 (n,d)
     Sb-126 (Z= 51, A=126), MT=107 (n,α)

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-123    U-235   Thermal   3.374170e-05   2.159470e-05 
     In-123    U-235   Fast      1.922360e-04   1.230310e-04 
     In-123    U-235   High      4.697520e-03   3.006420e-03 
     In-123    U-238   Fast      9.761330e-05   6.247250e-05 
     In-123    U-238   High      1.572290e-03   1.006260e-03 
     In-123   Pu-239   Thermal   1.948500e-04   1.247030e-04 
     In-123   Pu-239   Fast      3.361900e-04   2.151620e-04 
     In-123   Pu-239   High      8.406260e-03   5.380010e-03 
     In-123   Pu-241   Thermal   1.162570e-04   7.440410e-05 
     In-123   Pu-241   Fast      4.661270e-04   2.983210e-04 
     In-123m   U-235   Thermal   7.812110e-06   4.999770e-06 
     In-123m   U-235   Fast      3.881690e-05   2.484280e-05 
     In-123m   U-235   High      5.924800e-04   3.791880e-04 
     In-123m   U-238   Fast      1.971040e-05   1.261470e-05 
     In-123m   U-238   High      1.983060e-04   1.269160e-04 
     In-123m  Pu-239   Thermal   4.511300e-05   2.887230e-05 
     In-123m  Pu-239   Fast      6.788450e-05   4.344610e-05 
     In-123m  Pu-239   High      1.060250e-03   6.785600e-04 
     In-123m  Pu-241   Thermal   2.691660e-05   1.722660e-05 
     In-123m  Pu-241   Fast      9.412180e-05   6.023790e-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-123    U-235   Thermal   6.587260e-05   1.515070e-05 
     In-123    U-235   Fast      2.402620e-04   1.537680e-04 
     In-123    U-235   High      6.548280e-03   2.946730e-03 
     In-123    U-238   Fast      1.979820e-04   1.267080e-04 
     In-123    U-238   High      3.868950e-03   1.741030e-03 
     In-123   Pu-239   Thermal   2.104820e-04   1.347090e-04 
     In-123   Pu-239   Fast      3.624870e-04   2.319910e-04 
     In-123   Pu-239   High      9.762730e-03   5.662150e-03 
     In-123   Pu-241   Thermal   1.474830e-04   9.438880e-05 
     In-123   Pu-241   Fast      5.694800e-04   3.644680e-04 
     In-123m   U-235   Thermal   7.932930e-05   4.820100e-05 
     In-123m   U-235   Fast      1.457140e-04   8.565150e-05 
     In-123m   U-235   High      4.711920e-03   2.887940e-03 
     In-123m   U-238   Fast      2.431110e-04   1.555910e-04 
     In-123m   U-238   High      5.310230e-03   1.699270e-03 
     In-123m  Pu-239   Thermal   7.990680e-05   4.307400e-05 
     In-123m  Pu-239   Fast      1.264160e-04   6.819800e-05 
     In-123m  Pu-239   High      4.079490e-03   2.409220e-03 
     In-123m  Pu-241   Thermal   9.641940e-05   5.634740e-05 
     In-123m  Pu-241   Fast      3.241660e-04   1.882770e-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