Level energy(keV)   Spin & Parity       
       ground state      1/2-                  
       8.80341E+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)
     108.904755282 ± 0.000001405 (amu)  [mass excess = -88719.883 ± 1.309 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -215.521 ± 1.790 (keV) 
Strong Gamma-rays from Decay of Ag-109 (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 
         88.03            3.7          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           39.6 S 2         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ag-109.
     Figures of cross sections, Ag-109:  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
     Ag-109 (Z= 47, A=109), MT=  2 (Elastic scattering)
     Ag-109 (Z= 47, A=109), MT=  4 (Inelastic scattering)
     Ag-110 (Z= 47, A=110), MT= 16 (n,2n)
     Ag-111 (Z= 47, A=111), MT= 17 (n,3n)
     Cd-110 (Z= 48, A=110), MT= 28 (n,np)
     Cd-110 (Z= 48, A=110), MT=104 (n,d)
     Cd-111 (Z= 48, A=111), MT= 32 (n,nd)
     Cd-111 (Z= 48, A=111), MT=105 (n,t)
     In-113 (Z= 49, A=113), 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)
     Ag-109    U-235   High      2.544480e-10   1.628470e-10 
     Ag-109    U-238   High      1.903980e-12   1.218540e-12 
     Ag-109   Pu-239   High      9.631250e-08   6.164000e-08 
     Ag-109   Pu-241   Thermal   2.460900e-11   1.574980e-11 
     Ag-109   Pu-241   Fast      2.287480e-10   1.463990e-10 
     Ag-109m   U-235   High      3.050070e-09   1.952050e-09 
     Ag-109m   U-238   High      2.282300e-11   1.460670e-11 
     Ag-109m  Pu-239   High      1.154500e-06   7.388790e-07 
     Ag-109m  Pu-241   Thermal   1.604210e-10   1.026690e-10 
     Ag-109m  Pu-241   Fast      1.709790e-09   1.094270e-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)
     Ag-109    U-235   Thermal   3.112370e-04   9.711080e-07 
     Ag-109    U-235   Fast      8.124670e-04   2.986460e-06 
     Ag-109    U-235   High      1.173270e-02   7.507230e-03 
     Ag-109    U-238   Fast      2.518120e-03   3.301770e-06 
     Ag-109    U-238   High      1.121950e-02   7.180500e-03 
     Ag-109   Pu-239   Thermal   1.477270e-02   6.059180e-06 
     Ag-109   Pu-239   Fast      1.035880e-02   3.934840e-06 
     Ag-109   Pu-239   High      2.477130e-02   1.584920e-02 
     Ag-109   Pu-241   Thermal   2.586490e-02   1.655350e-02 
     Ag-109   Pu-241   Fast      2.350260e-02   1.504170e-02 
     Ag-109m   U-235   Thermal   3.110810e-04   9.677310e-07 
     Ag-109m   U-235   Fast      8.120600e-04   2.996710e-06 
     Ag-109m   U-235   High      1.172680e-02   7.503630e-03 
     Ag-109m   U-238   Fast      2.516860e-03   3.351130e-06 
     Ag-109m   U-238   High      1.121390e-02   7.176910e-03 
     Ag-109m  Pu-239   Thermal   1.476540e-02   6.345100e-06 
     Ag-109m  Pu-239   Fast      1.035360e-02   4.114580e-06 
     Ag-109m  Pu-239   High      2.475880e-02   1.584180e-02 
     Ag-109m  Pu-241   Thermal   2.585200e-02   1.654530e-02 
     Ag-109m  Pu-241   Fast      2.349090e-02   1.503410e-02 
    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