Level energy(keV)   Spin & Parity       
       ground state      11/2-                 
       2.46000E+01       3/2+                  
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)
     122.905725221 ± 0.000002601 (amu)  [mass excess = -87816.391 ± 2.423 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1408.435 ± 2.976 (keV) 
Strong Gamma-rays from Decay of Sn-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 
        160.32           85.7          B- 
        381.4             0.04         B- 
        541.8             0.02         B- 
        160.33          2.E-03         B- 
       1030.23            0.03         B- 
       1088.64            0.6          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-           129.2 D 4        
       B-           40.06 M 1        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sn-123.
     Figures of cross sections, Sn-123:  type-1:  type-2:  type-3.
       type-1: total, elastic and inelastic scattering, capture and fision cross sections
       type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
       type-3: threshold reaction cross sections
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-122 (Z= 50, A=122), MT=102 (n,γ)
     Sn-123 (Z= 50, A=123), MT=  2 (Elastic scattering)
     Sn-123 (Z= 50, A=123), MT=  4 (Inelastic scattering)
     Sn-124 (Z= 50, A=124), MT= 16 (n,2n)
     Sb-123 (Z= 51, A=123), MT=103 (n,p)
     Sb-124 (Z= 51, A=124), MT= 28 (n,np)
     Sb-124 (Z= 51, A=124), MT=104 (n,d)
     Sb-125 (Z= 51, A=125), MT= 32 (n,nd)
     Sb-125 (Z= 51, A=125), MT=105 (n,t)
     Te-126 (Z= 52, A=126), MT=107 (n,α)
     Te-127 (Z= 52, A=127), 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-123    U-235   Thermal   7.863460e-06   3.538550e-06 
     Sn-123    U-235   Fast      3.938510e-05   2.520640e-05 
     Sn-123    U-235   High      5.547210e-04   3.550210e-04 
     Sn-123    U-238   Fast      3.317740e-06   2.123350e-06 
     Sn-123    U-238   High      4.660140e-05   2.982490e-05 
     Sn-123   Pu-239   Thermal   1.033050e-04   6.611500e-05 
     Sn-123   Pu-239   Fast      1.992600e-04   1.275270e-04 
     Sn-123   Pu-239   High      2.710750e-03   1.734880e-03 
     Sn-123   Pu-241   Thermal   1.629190e-05   1.042680e-05 
     Sn-123   Pu-241   Fast      9.013370e-05   5.768550e-05 
     Sn-123m   U-235   Thermal   3.258830e-06   1.042830e-06 
     Sn-123m   U-235   Fast      1.405470e-05   8.994960e-06 
     Sn-123m   U-235   High      1.209440e-04   7.740440e-05 
     Sn-123m   U-238   Fast      1.183940e-06   7.577210e-07 
     Sn-123m   U-238   High      1.016040e-05   6.502660e-06 
     Sn-123m  Pu-239   Thermal   4.281240e-05   2.739990e-05 
     Sn-123m  Pu-239   Fast      7.110620e-05   4.550790e-05 
     Sn-123m  Pu-239   High      5.910170e-04   3.782510e-04 
     Sn-123m  Pu-241   Thermal   6.751810e-06   4.321170e-06 
     Sn-123m  Pu-241   Fast      3.216440e-05   2.058520e-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)
     Sn-123    U-235   Thermal   9.971380e-06   4.117340e-06 
     Sn-123    U-235   Fast      4.707350e-05   2.637900e-05 
     Sn-123    U-235   High      7.642660e-04   4.122150e-04 
     Sn-123    U-238   Fast      9.653150e-06   6.178010e-06 
     Sn-123    U-238   High      1.704080e-04   1.090610e-04 
     Sn-123   Pu-239   Thermal   1.100400e-04   6.646520e-05 
     Sn-123   Pu-239   Fast      2.108590e-04   1.280690e-04 
     Sn-123   Pu-239   High      3.023160e-03   1.761990e-03 
     Sn-123   Pu-241   Thermal   2.101140e-05   1.144470e-05 
     Sn-123   Pu-241   Fast      1.083570e-04   6.051660e-05 
     Sn-123m   U-235   Thermal   1.463530e-04   6.367980e-06 
     Sn-123m   U-235   Fast      3.923420e-04   9.259050e-05 
     Sn-123m   U-235   High      1.117160e-02   2.620310e-03 
     Sn-123m   U-238   Fast      4.359410e-04   1.415790e-04 
     Sn-123m   U-238   High      9.065530e-03   2.112110e-03 
     Sn-123m  Pu-239   Thermal   3.264650e-04   1.501180e-04 
     Sn-123m  Pu-239   Fast      5.484090e-04   2.523100e-04 
     Sn-123m  Pu-239   High      1.412080e-02   4.625360e-03 
     Sn-123m  Pu-241   Thermal   2.459340e-04   1.128720e-04 
     Sn-123m  Pu-241   Fast      9.075880e-04   2.970860e-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