46-Pd-106



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)
     105.903480426 ± 0.000001187 (amu)  [mass excess = -89907.404 ± 1.106 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2965.142 ± 2.817 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Pd-106.
     Figures of cross sections, Pd-106:  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-105 (Z= 46, A=105), MT=102 (n,γ)
     Pd-106 (Z= 46, A=106), MT=  2 (Elastic scattering)
     Pd-106 (Z= 46, A=106), MT=  4 (Inelastic scattering)
     Pd-107 (Z= 46, A=107), MT= 16 (n,2n)
     Pd-108 (Z= 46, A=108), MT= 17 (n,3n)
     Ag-107 (Z= 47, A=107), MT= 28 (n,np)
     Ag-107 (Z= 47, A=107), MT=104 (n,d)
     Ag-109 (Z= 47, A=109), MT= 33 (n,nt)
     Cd-108 (Z= 48, A=108), MT=106 (n,3He)
     Cd-110 (Z= 48, A=110), 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-106    U-235   High      2.152950e-09   1.377880e-09 
     Pd-106    U-238   High      2.512740e-11   1.608150e-11 
     Pd-106   Pu-239   Thermal   9.148560e-09   5.855080e-09 
     Pd-106   Pu-239   Fast      1.529750e-08   9.790420e-09 
     Pd-106   Pu-239   High      2.791810e-06   1.786760e-06 
     Pd-106   Pu-241   Thermal   8.061300e-11   5.159240e-11 
     Pd-106   Pu-241   Fast      2.917810e-10   1.867400e-10 
    -----------------------------------------------------------
    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-106    U-235   Thermal   4.008720e-03   6.758140e-06 
     Pd-106    U-235   Fast      5.314650e-03   9.294600e-06 
     Pd-106    U-235   High      1.613270e-02   6.448950e-04 
     Pd-106    U-238   Fast      2.493380e-02   3.635140e-05 
     Pd-106    U-238   High      2.463620e-02   6.931720e-04 
     Pd-106   Pu-239   Thermal   4.349800e-02   8.700390e-04 
     Pd-106   Pu-239   Fast      4.364310e-02   6.112590e-04 
     Pd-106   Pu-239   High      3.579470e-02   2.861980e-03 
     Pd-106   Pu-241   Thermal   6.104550e-02   1.220810e-03 
     Pd-106   Pu-241   Fast      6.238620e-02   8.760480e-04 
    -----------------------------------------------------------
    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