Level energy(keV)   Spin & Parity       
       ground state      1/2+                  
       2.63700E+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)
     112.904408133 ± 0.000000445 (amu)  [mass excess = -89043.251 ± 0.415 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     322.571 ± 0.790 (keV) 
Strong Gamma-rays from Decay of Cd-113 (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 
        263.7             0.03         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-           8.04E15 Y 5      
       B-           14.1 Y 5         
       IT           14.1 Y 5         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Cd-113.
     Figures of cross sections, Cd-113:  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
     Cd-112 (Z= 48, A=112), MT=102 (n,γ)
     Cd-113 (Z= 48, A=113), MT=  2 (Elastic scattering)
     Cd-113 (Z= 48, A=113), MT=  4 (Inelastic scattering)
     Cd-114 (Z= 48, A=114), MT= 16 (n,2n)
     In-113 (Z= 49, A=113), MT=103 (n,p)
     In-115 (Z= 49, A=115), MT= 32 (n,nd)
     In-115 (Z= 49, A=115), MT=105 (n,t)
     Sn-114 (Z= 50, A=114), MT=111 (n,2p)
     Sn-115 (Z= 50, A=115), MT=106 (n,3He)
     Sn-116 (Z= 50, A=116), MT=107 (n,α)
     Sn-117 (Z= 50, A=117), 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-113    U-235   Thermal   2.632990e-12   1.685110e-12 
     Cd-113    U-235   Fast      3.564460e-12   2.281250e-12 
     Cd-113    U-235   High      1.666110e-08   1.066310e-08 
     Cd-113    U-238   Fast      1.599450e-14   1.023650e-14 
     Cd-113    U-238   High      1.989870e-10   1.273520e-10 
     Cd-113   Pu-239   High      1.033440e-06   6.614020e-07 
     Cd-113m   U-235   Thermal   8.619100e-12   5.516220e-12 
     Cd-113m   U-235   Fast      1.349040e-11   8.633820e-12 
     Cd-113m   U-235   High      1.032030e-07   6.605000e-08 
     Cd-113m   U-238   Fast      6.053410e-14   3.874170e-14 
     Cd-113m   U-238   High      1.232580e-09   7.888450e-10 
     Cd-113m  Pu-239   High      6.401380e-06   4.096880e-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)
     Cd-113    U-235   Thermal   1.395600e-04   5.674760e-06 
     Cd-113    U-235   Fast      3.202740e-04   9.255790e-06 
     Cd-113    U-235   High      1.075450e-02   8.634080e-04 
     Cd-113    U-238   Fast      4.539230e-04   5.016180e-05 
     Cd-113    U-238   High      9.007100e-03   5.429940e-04 
     Cd-113   Pu-239   Thermal   8.034630e-04   3.617490e-06 
     Cd-113   Pu-239   Fast      1.256020e-03   5.660460e-06 
     Cd-113   Pu-239   High      1.275040e-02   2.944530e-03 
     Cd-113   Pu-241   Thermal   1.495210e-03   6.282470e-06 
     Cd-113   Pu-241   Fast      2.096750e-03   1.072740e-05 
     Cd-113m   U-235   Thermal   2.269010e-06   6.234400e-07 
     Cd-113m   U-235   Fast      5.207260e-06   1.849000e-06 
     Cd-113m   U-235   High      1.747440e-04   4.849050e-05 
     Cd-113m   U-238   Fast      7.380690e-06   2.169440e-06 
     Cd-113m   U-238   High      1.464420e-04   4.000960e-05 
     Cd-113m  Pu-239   Thermal   1.306410e-05   3.514250e-06 
     Cd-113m  Pu-239   Fast      2.042260e-05   5.482920e-06 
     Cd-113m  Pu-239   High      2.109070e-04   9.016180e-05 
     Cd-113m  Pu-241   Thermal   2.431180e-05   6.531770e-06 
     Cd-113m  Pu-241   Fast      3.409280e-05   9.142760e-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