Level energy(keV)   Spin & Parity       
       ground state      9/2+                  
       3.15302E+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)
     116.904515678 ± 0.000005239 (amu)  [mass excess = -88943.073 ± 4.881 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1454.710 ± 4.857 (keV) 
Strong Gamma-rays from Decay of In-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 
        158.6            87.           B- 
        396.6             0.17         B- 
        552.9           100.           B- 
        158.6            15.87         B- 
        861.6             0.02         B- 
       1020.3           7.E-03         B- 
        315.30           19.12         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 
       B-           43.2 M 3         
       B-           116.2 M 3        
       IT           116.2 M 3        
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-117 (Z= 50, A=117), MT=103 (n,p)
     Sn-118 (Z= 50, A=118), MT= 28 (n,np)
     Sn-118 (Z= 50, A=118), MT=104 (n,d)
     Sn-119 (Z= 50, A=119), MT= 32 (n,nd)
     Sn-119 (Z= 50, A=119), MT=105 (n,t)
     Sb-121 (Z= 51, A=121), 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-117    U-235   Thermal   3.663590e-09   2.344700e-09 
     In-117    U-235   Fast      5.679150e-09   3.634660e-09 
     In-117    U-235   High      2.058540e-06   1.317470e-06 
     In-117    U-238   Fast      9.313550e-11   5.960670e-11 
     In-117    U-238   High      3.456300e-08   2.212040e-08 
     In-117   Pu-239   Thermal   7.038930e-08   4.504910e-08 
     In-117   Pu-239   Fast      1.292720e-07   8.273390e-08 
     In-117   Pu-239   High      3.766670e-05   2.410670e-05 
     In-117   Pu-241   Thermal   4.151620e-10   2.657030e-10 
     In-117   Pu-241   Fast      4.136920e-09   2.647630e-09 
     In-117m   U-235   Thermal   8.482210e-10   5.428620e-10 
     In-117m   U-235   Fast      1.146750e-09   7.339220e-10 
     In-117m   U-235   High      2.596360e-07   1.661680e-07 
     In-117m   U-238   Fast      1.880620e-11   1.203600e-11 
     In-117m   U-238   High      4.359300e-09   2.789950e-09 
     In-117m  Pu-239   Thermal   1.629700e-08   1.043010e-08 
     In-117m  Pu-239   Fast      2.610300e-08   1.670590e-08 
     In-117m  Pu-239   High      4.750760e-06   3.040490e-06 
     In-117m  Pu-241   Thermal   9.612120e-11   6.151760e-11 
     In-117m  Pu-241   Fast      8.353400e-10   5.346180e-10 
    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-117    U-235   Thermal   7.717760e-05   8.137990e-06 
     In-117    U-235   Fast      2.200660e-04   7.644980e-05 
     In-117    U-235   High      6.413550e-03   1.622570e-03 
     In-117    U-238   Fast      2.236540e-04   7.795940e-05 
     In-117    U-238   High      3.591120e-03   3.338620e-04 
     In-117   Pu-239   Thermal   2.692240e-04   6.805390e-05 
     In-117   Pu-239   Fast      4.244330e-04   1.468460e-04 
     In-117   Pu-239   High      7.275800e-03   2.498890e-03 
     In-117   Pu-241   Thermal   1.405820e-04   4.878920e-05 
     In-117   Pu-241   Fast      5.242350e-04   1.820660e-04 
     In-117m   U-235   Thermal   9.476830e-05   1.011260e-05 
     In-117m   U-235   Fast      2.777120e-04   1.163040e-04 
     In-117m   U-235   High      7.985770e-03   2.433980e-03 
     In-117m   U-238   Fast      2.850520e-04   8.691890e-05 
     In-117m   U-238   High      4.574660e-03   5.193010e-04 
     In-117m  Pu-239   Thermal   3.307150e-04   1.008060e-04 
     In-117m  Pu-239   Fast      5.173070e-04   2.160800e-04 
     In-117m  Pu-239   High      8.008740e-03   2.441750e-03 
     In-117m  Pu-241   Thermal   1.792480e-04   7.517960e-05 
     In-117m  Pu-241   Fast      6.672350e-04   2.797380e-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