Level energy(keV)   Spin & Parity       
       ground state      1/2+                  
       1.81000E+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)
     114.905437513 ± 0.000000765 (amu)  [mass excess = -88084.389 ± 0.713 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1451.955 ± 0.713 (keV) 
Strong Gamma-rays from Decay of Cd-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 
        336.24           45.9          B- 
        492.35            8.03         B- 
        527.90           27.45         B- 
        484.47            0.29         B- 
        933.84            2.           B- 
       1290.59            0.89         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-           53.46 H 5        
       B-           44.56 D 24       
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Cd-114 (Z= 48, A=114), MT=102 (n,γ)
     Cd-116 (Z= 48, A=116), MT= 16 (n,2n)
     In-115 (Z= 49, A=115), MT=103 (n,p)
     Sn-117 (Z= 50, A=117), MT=106 (n,3He)
     Sn-118 (Z= 50, A=118), MT=107 (n,α)
     Sn-119 (Z= 50, A=119), 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)
     Cd-115    U-235   Thermal   1.502230e-08   4.807140e-09 
     Cd-115    U-235   Fast      6.390570e-09   4.089960e-09 
     Cd-115    U-235   High      5.558420e-04   3.557400e-04 
     Cd-115    U-238   Fast      1.053750e-10   6.744000e-11 
     Cd-115    U-238   High      5.177820e-08   3.313800e-08 
     Cd-115   Pu-239   Thermal   2.065890e-08   1.322170e-08 
     Cd-115   Pu-239   Fast      5.105050e-08   3.267230e-08 
     Cd-115   Pu-239   High      2.286360e-05   1.463270e-05 
     Cd-115   Pu-241   Thermal   1.125720e-10   7.204610e-11 
     Cd-115   Pu-241   Fast      3.092960e-09   1.979500e-09 
     Cd-115m   U-235   Thermal   4.917550e-08   1.573610e-08 
     Cd-115m   U-235   Fast      2.418630e-08   1.547930e-08 
     Cd-115m   U-235   High      3.443020e-03   1.101770e-03 
     Cd-115m   U-238   Fast      3.988130e-10   2.552410e-10 
     Cd-115m   U-238   High      3.207270e-07   2.052660e-07 
     Cd-115m  Pu-239   Thermal   6.762710e-08   4.328140e-08 
     Cd-115m  Pu-239   Fast      1.932100e-07   1.236550e-07 
     Cd-115m  Pu-239   High      1.416230e-04   9.063870e-05 
     Cd-115m  Pu-241   Thermal   3.685060e-10   2.358440e-10 
     Cd-115m  Pu-241   Fast      1.170590e-08   7.491780e-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)
     Cd-115    U-235   Thermal   1.192010e-04   7.740480e-06 
     Cd-115    U-235   Fast      3.206920e-04   1.319910e-05 
     Cd-115    U-235   High      7.137690e-03   3.588930e-04 
     Cd-115    U-238   Fast      3.564930e-04   1.394140e-05 
     Cd-115    U-238   High      8.140060e-03   4.203230e-04 
     Cd-115   Pu-239   Thermal   4.040200e-04   2.692010e-05 
     Cd-115   Pu-239   Fast      7.719610e-04   3.906450e-05 
     Cd-115   Pu-239   High      1.195150e-02   1.002900e-03 
     Cd-115   Pu-241   Thermal   3.613000e-04   4.024950e-05 
     Cd-115   Pu-241   Fast      1.033320e-03   2.323960e-04 
     Cd-115m   U-235   Thermal   6.406090e-06   3.686740e-06 
     Cd-115m   U-235   Fast      1.727680e-05   3.973670e-06 
     Cd-115m   U-235   High      3.795630e-03   2.183990e-04 
     Cd-115m   U-238   Fast      1.921320e-05   1.203260e-05 
     Cd-115m   U-238   High      4.386150e-04   2.740430e-04 
     Cd-115m  Pu-239   Thermal   2.178220e-05   1.359220e-05 
     Cd-115m  Pu-239   Fast      4.165790e-05   2.570030e-05 
     Cd-115m  Pu-239   High      7.712730e-04   4.227460e-04 
     Cd-115m  Pu-241   Thermal   1.947220e-05   8.762490e-06 
     Cd-115m  Pu-241   Fast      5.567510e-05   1.280530e-05 
    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