Level energy(keV)   Spin & Parity       
       ground state      1/2+                  
       8.95350E+01       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)
     118.903311172 ± 0.000000779 (amu)  [mass excess = -90065.063 ± 0.726 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -590.846 ± 7.689 (keV) 
Strong Gamma-rays from Decay of Sn-119 (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 
         23.88           16.5          IT 
         65.66            0.02         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 
       IT           293 D 1          
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sn-119.
     Figures of cross sections, Sn-119:  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-118 (Z= 50, A=118), MT=102 (n,γ)
     Sn-119 (Z= 50, A=119), MT=  2 (Elastic scattering)
     Sn-119 (Z= 50, A=119), MT=  4 (Inelastic scattering)
     Sn-120 (Z= 50, A=120), MT= 16 (n,2n)
     Sb-121 (Z= 51, A=121), MT=105 (n,t)
     Te-122 (Z= 52, A=122), MT=107 (n,α)
     Te-123 (Z= 52, A=123), 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-119    U-235   Thermal   3.457700e-10   2.212930e-10 
     Sn-119    U-235   Fast      6.839000e-10   4.376960e-10 
     Sn-119    U-235   High      6.457060e-08   4.132520e-08 
     Sn-119    U-238   Fast      5.030410e-12   3.219460e-12 
     Sn-119    U-238   High      5.258530e-10   3.365460e-10 
     Sn-119   Pu-239   Thermal   1.118340e-08   7.157370e-09 
     Sn-119   Pu-239   Fast      1.901590e-08   1.217020e-08 
     Sn-119   Pu-239   High      1.858250e-06   1.189280e-06 
     Sn-119   Pu-241   Thermal   9.785120e-11   6.262490e-11 
     Sn-119   Pu-241   Fast      5.208540e-10   3.333470e-10 
     Sn-119m   U-235   Thermal   1.131880e-09   7.244010e-10 
     Sn-119m   U-235   Fast      2.588350e-09   1.656550e-09 
     Sn-119m   U-235   High      3.999660e-07   2.559780e-07 
     Sn-119m   U-238   Fast      1.903850e-11   1.218470e-11 
     Sn-119m   U-238   High      3.257260e-09   2.084650e-09 
     Sn-119m  Pu-239   Thermal   3.660900e-08   2.342980e-08 
     Sn-119m  Pu-239   Fast      7.196930e-08   4.606040e-08 
     Sn-119m  Pu-239   High      1.151040e-05   7.366670e-06 
     Sn-119m  Pu-241   Thermal   3.203160e-10   2.050030e-10 
     Sn-119m  Pu-241   Fast      1.971270e-09   1.261610e-09 
    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-119    U-235   Thermal   1.285440e-04   1.030020e-05 
     Sn-119    U-235   Fast      3.494760e-04   2.802510e-05 
     Sn-119    U-235   High      1.085630e-02   1.192530e-03 
     Sn-119    U-238   Fast      3.973530e-04   4.369260e-05 
     Sn-119    U-238   High      7.267400e-03   7.985890e-04 
     Sn-119   Pu-239   Thermal   3.224490e-04   2.579890e-05 
     Sn-119   Pu-239   Fast      5.500940e-04   6.051760e-05 
     Sn-119   Pu-239   High      1.252670e-02   1.377060e-03 
     Sn-119   Pu-241   Thermal   2.316060e-04   7.409910e-05 
     Sn-119   Pu-241   Fast      8.232680e-04   1.318230e-04 
     Sn-119m   U-235   Thermal   6.688250e-07   1.538300e-07 
     Sn-119m   U-235   Fast      1.753770e-06   7.891970e-07 
     Sn-119m   U-235   High      5.115350e-05   1.636920e-05 
     Sn-119m   U-238   Fast      1.508440e-06   6.787950e-07 
     Sn-119m   U-238   High      2.822530e-05   1.270140e-05 
     Sn-119m  Pu-239   Thermal   1.834180e-06   8.253810e-07 
     Sn-119m  Pu-239   Fast      3.245220e-06   1.460350e-06 
     Sn-119m  Pu-239   High      8.588850e-05   2.748430e-05 
     Sn-119m  Pu-241   Thermal   1.001410e-06   4.506340e-07 
     Sn-119m  Pu-241   Fast      3.669490e-06   1.651270e-06 
    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