46-Pd-108



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      0+                    
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)
     107.903891640 ± 0.000001191 (amu)  [mass excess = -89524.361 ± 1.110 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1917.673 ± 2.634 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Pd-108.
     Figures of cross sections, Pd-108:  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
     Pd-107 (Z= 46, A=107), MT=102 (n,γ)
     Pd-108 (Z= 46, A=108), MT=  2 (Elastic scattering)
     Pd-108 (Z= 46, A=108), MT=  4 (Inelastic scattering)
     Pd-110 (Z= 46, A=110), MT= 17 (n,3n)
     Ag-109 (Z= 47, A=109), MT= 28 (n,np)
     Ag-109 (Z= 47, A=109), MT=104 (n,d)
     Ag-110 (Z= 47, A=110), MT= 32 (n,nd)
     Ag-110 (Z= 47, A=110), MT= 41 (n,2np)
     Ag-110 (Z= 47, A=110), MT=105 (n,t)
     Ag-111 (Z= 47, A=111), MT= 33 (n,nt)
     Cd-110 (Z= 48, A=110), MT=106 (n,3He)
     Cd-111 (Z= 48, A=111), MT=107 (n,α)
     Cd-112 (Z= 48, A=112), 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)
    -----------------------------------------------------------
     Pd-108    U-235   High      3.624970e-07   2.319980e-07 
     Pd-108    U-238   High      8.879670e-09   5.682980e-09 
     Pd-108   Pu-239   Thermal   2.879540e-06   1.842910e-06 
     Pd-108   Pu-239   Fast      4.339290e-06   2.777150e-06 
     Pd-108   Pu-239   High      8.072230e-05   5.166230e-05 
     Pd-108   Pu-241   Thermal   1.220200e-07   7.809260e-08 
     Pd-108   Pu-241   Fast      5.685720e-07   3.638860e-07 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Pd-108    U-235   Thermal   5.405300e-04   7.224150e-07 
     Pd-108    U-235   Fast      1.305740e-03   2.412710e-06 
     Pd-108    U-235   High      1.180150e-02   1.295950e-03 
     Pd-108    U-238   Fast      6.017140e-03   2.904330e-06 
     Pd-108    U-238   High      1.224280e-02   1.956030e-03 
     Pd-108   Pu-239   Thermal   2.163900e-02   8.655720e-04 
     Pd-108   Pu-239   Fast      2.002580e-02   1.602190e-03 
     Pd-108   Pu-239   High      2.400200e-02   2.638080e-03 
     Pd-108   Pu-241   Thermal   3.771070e-02   3.015720e-03 
     Pd-108   Pu-241   Fast      3.539870e-02   3.896210e-03 
    -----------------------------------------------------------
    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