Level energy(keV)   Spin & Parity       
       ground state      1/2+                  
       3.14580E+02       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)
     116.902953983 ± 0.000000519 (amu)  [mass excess = -90397.782 ± 0.483 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1758.218 ± 8.445 (keV) 
Strong Gamma-rays from Decay of Sn-117 (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 
        156.02            2.11         IT 
        158.56           86.4          IT 
        314.3           4.E-04         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           13.60 D 4        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sn-117.
     Figures of cross sections, Sn-117:  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-116 (Z= 50, A=116), MT=102 (n,γ)
     Sn-117 (Z= 50, A=117), MT=  2 (Elastic scattering)
     Sn-117 (Z= 50, A=117), MT=  4 (Inelastic scattering)
     Sn-118 (Z= 50, A=118), MT= 16 (n,2n)
     Sn-119 (Z= 50, A=119), MT= 17 (n,3n)
     Te-120 (Z= 52, A=120), 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)
     Sn-117    U-235   Thermal   1.165800e-13   7.461160e-14 
     Sn-117    U-235   Fast      1.330670e-13   8.516300e-14 
     Sn-117    U-235   High      2.575030e-10   1.648020e-10 
     Sn-117    U-238   High      7.235880e-13   4.630970e-13 
     Sn-117   Pu-239   Thermal   6.855110e-12   4.387270e-12 
     Sn-117   Pu-239   Fast      1.251710e-11   8.010940e-12 
     Sn-117   Pu-239   High      2.281080e-08   1.459890e-08 
     Sn-117   Pu-241   Thermal   4.423310e-15   2.830920e-15 
     Sn-117   Pu-241   Fast      6.745630e-14   4.317200e-14 
     Sn-117m   U-235   Thermal   3.816260e-13   2.442410e-13 
     Sn-117m   U-235   Fast      5.036180e-13   3.223150e-13 
     Sn-117m   U-235   High      1.595040e-09   1.020820e-09 
     Sn-117m   U-238   High      4.482080e-12   2.868540e-12 
     Sn-117m  Pu-239   Thermal   2.244020e-11   1.436180e-11 
     Sn-117m  Pu-239   Fast      4.737330e-11   3.031890e-11 
     Sn-117m  Pu-239   High      1.412960e-07   9.042920e-08 
     Sn-117m  Pu-241   Thermal   1.447970e-14   9.267040e-15 
     Sn-117m  Pu-241   Fast      2.553010e-13   1.633930e-13 
    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-117    U-235   Thermal   1.273100e-04   8.147840e-05 
     Sn-117    U-235   Fast      3.669760e-04   2.348650e-04 
     Sn-117    U-235   High      1.063800e-02   6.808340e-03 
     Sn-117    U-238   Fast      3.744460e-04   2.875630e-06 
     Sn-117    U-238   High      6.011120e-03   3.847120e-03 
     Sn-117   Pu-239   Thermal   4.441720e-04   2.842700e-04 
     Sn-117   Pu-239   Fast      6.980880e-04   4.467770e-04 
     Sn-117   Pu-239   High      1.151260e-02   7.368040e-03 
     Sn-117   Pu-241   Thermal   2.354040e-04   1.506580e-04 
     Sn-117   Pu-241   Fast      8.772030e-04   5.614100e-04 
     Sn-117m   U-235   Thermal   1.157660e-06   7.409030e-07 
     Sn-117m   U-235   Fast      3.301000e-06   2.112640e-06 
     Sn-117m   U-235   High      9.620480e-05   6.157090e-05 
     Sn-117m   U-238   Fast      3.354810e-06   2.147080e-06 
     Sn-117m   U-238   High      5.386680e-05   3.447470e-05 
     Sn-117m  Pu-239   Thermal   4.038380e-06   2.584560e-06 
     Sn-117m  Pu-239   Fast      6.366540e-06   4.074570e-06 
     Sn-117m  Pu-239   High      1.092780e-04   6.993810e-05 
     Sn-117m  Pu-241   Thermal   2.108720e-06   1.349580e-06 
     Sn-117m  Pu-241   Fast      7.863530e-06   5.032660e-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