Level energy(keV)   Spin & Parity       
       ground state      1/2-                  
       4.11000E+01       7/2+                  
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)
     114.908767355 ± 0.000019611 (amu)  [mass excess = -84982.661 ± 18.268 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     3101.728 ± 18.276 (keV) 
Strong Gamma-rays from Decay of Ag-115 (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 
        131.5          * 60.83         B- 
        229.1          * 79.           B- 
        388.9          * 41.08         B- 
        212.8             4.45         B- 
        229.1            18.           B- 
        472.7             3.98         B- 
         41.1             0.01         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-           20.0 M 5         
       B-           18.0 S 7         
       IT           18.0 S 7         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Cd-116 (Z= 48, A=116), MT= 28 (n,np)
     Cd-116 (Z= 48, A=116), MT=104 (n,d)

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)
     Ag-115    U-235   Thermal   2.075480e-06   1.328310e-06 
     Ag-115    U-235   Fast      8.761120e-07   5.607110e-07 
     Ag-115    U-235   High      3.526660e-05   2.257060e-05 
     Ag-115    U-238   Fast      7.602030e-08   4.865290e-08 
     Ag-115    U-238   High      7.611270e-06   4.871210e-06 
     Ag-115   Pu-239   Thermal   1.901600e-06   1.217020e-06 
     Ag-115   Pu-239   Fast      3.801340e-06   2.432860e-06 
     Ag-115   Pu-239   High      2.170540e-04   1.389140e-04 
     Ag-115   Pu-241   Thermal   8.992260e-08   5.755040e-08 
     Ag-115   Pu-241   Fast      9.220670e-07   5.901230e-07 
     Ag-115m   U-235   Thermal   1.352960e-05   8.658990e-06 
     Ag-115m   U-235   Fast      6.548570e-06   4.191080e-06 
     Ag-115m   U-235   High      4.227410e-04   2.705540e-04 
     Ag-115m   U-238   Fast      5.682200e-07   3.636600e-07 
     Ag-115m   U-238   High      9.123630e-05   5.839120e-05 
     Ag-115m  Pu-239   Thermal   1.239610e-05   7.933530e-06 
     Ag-115m  Pu-239   Fast      2.841340e-05   1.818460e-05 
     Ag-115m  Pu-239   High      2.601820e-03   1.665170e-03 
     Ag-115m  Pu-241   Thermal   5.861870e-07   3.751600e-07 
     Ag-115m  Pu-241   Fast      6.892060e-06   4.410920e-06 
    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)
     Ag-115    U-235   Thermal   9.140500e-05   1.020270e-05 
     Ag-115    U-235   Fast      2.622660e-04   8.009240e-05 
     Ag-115    U-235   High      5.219060e-03   3.078270e-03 
     Ag-115    U-238   Fast      2.952560e-04   9.019820e-05 
     Ag-115    U-238   High      6.697560e-03   8.483910e-04 
     Ag-115   Pu-239   Thermal   3.281660e-04   1.001390e-04 
     Ag-115   Pu-239   Fast      6.243060e-04   1.904610e-04 
     Ag-115   Pu-239   High      8.425450e-03   2.589710e-03 
     Ag-115   Pu-241   Thermal   2.992340e-04   1.267880e-04 
     Ag-115   Pu-241   Fast      8.529260e-04   3.613110e-04 
     Ag-115m   U-235   Thermal   4.321290e-05   6.926510e-06 
     Ag-115m   U-235   Fast      9.578720e-05   6.130380e-05 
     Ag-115m   U-235   High      2.171380e-03   1.387330e-03 
     Ag-115m   U-238   Fast      1.018350e-04   4.579950e-05 
     Ag-115m   U-238   High      2.380690e-03   1.070290e-03 
     Ag-115m  Pu-239   Thermal   1.234790e-04   5.559140e-05 
     Ag-115m  Pu-239   Fast      2.393260e-04   1.077550e-04 
     Ag-115m  Pu-239   High      5.231470e-03   2.352830e-03 
     Ag-115m  Pu-241   Thermal   1.032120e-04   6.605560e-05 
     Ag-115m  Pu-241   Fast      2.988080e-04   1.346130e-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