47-Ag-107



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      1/2-                  
       9.31250E+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)
     106.905091611 ± 0.000002557 (amu)  [mass excess = -88406.595 ± 2.382 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1416.347 ± 2.567 (keV) 
Strong Gamma-rays from Decay of Ag-107 (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 
  ----------------------------------------------------------
         93.12            4.67         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           44.3 S 2         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ag-107.
     Figures of cross sections, Ag-107:  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-107 (Z= 47, A=107), MT=  2 (Elastic scattering)
     Ag-107 (Z= 47, A=107), MT=  4 (Inelastic scattering)
     Ag-109 (Z= 47, A=109), MT= 17 (n,3n)
     Cd-108 (Z= 48, A=108), MT= 28 (n,np)
     Cd-108 (Z= 48, A=108), 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-107    U-235   High      3.779720e-13   2.419020e-13 
     Ag-107   Pu-239   Thermal   1.289900e-12   8.255370e-13 
     Ag-107   Pu-239   Fast      2.439850e-12   1.561500e-12 
     Ag-107   Pu-239   High      3.367080e-09   2.154930e-09 
     Ag-107   Pu-241   Fast      2.599940e-14   1.663960e-14 
    -----------------------------------------------------------
     Ag-107m   U-235   High      4.530760e-12   2.899680e-12 
     Ag-107m   U-238   High      1.025640e-14   6.564140e-15 
     Ag-107m  Pu-239   Thermal   8.408570e-12   5.381480e-12 
     Ag-107m  Pu-239   Fast      1.823680e-11   1.167160e-11 
     Ag-107m  Pu-239   High      4.036130e-08   2.583120e-08 
     Ag-107m  Pu-241   Thermal   2.089810e-14   1.337480e-14 
     Ag-107m  Pu-241   Fast      1.943350e-13   1.243740e-13 
    -----------------------------------------------------------
    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-107    U-235   Thermal   1.457600e-03   4.321690e-06 
     Ag-107    U-235   Fast      3.007820e-03   1.544180e-05 
     Ag-107    U-235   High      1.282460e-02   1.414160e-03 
     Ag-107    U-238   Fast      1.433200e-02   1.267590e-04 
     Ag-107    U-238   High      1.678290e-02   1.609420e-04 
     Ag-107   Pu-239   Thermal   3.328650e-02   1.332080e-03 
     Ag-107   Pu-239   Fast      3.219870e-02   1.932650e-03 
     Ag-107   Pu-239   High      2.863610e-02   3.148540e-03 
     Ag-107   Pu-241   Thermal   4.879730e-02   6.585200e-05 
     Ag-107   Pu-241   Fast      4.898330e-02   5.397980e-03 
    -----------------------------------------------------------
     Ag-107m   U-235   High      4.530760e-12   2.895390e-12 
     Ag-107m   U-238   High      1.025640e-14   6.557030e-15 
     Ag-107m  Pu-239   Thermal   8.408570e-12   5.381480e-12 
     Ag-107m  Pu-239   Fast      1.823680e-11   1.167160e-11 
     Ag-107m  Pu-239   High      4.036130e-08   2.581450e-08 
     Ag-107m  Pu-241   Thermal   2.089810e-14   1.337480e-14 
     Ag-107m  Pu-241   Fast      1.943350e-13   1.243740e-13 
    -----------------------------------------------------------
    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