48-Cd-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)
     107.904183440 ± 0.000001206 (amu)  [mass excess = -89252.551 ± 1.124 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -5132.610 ± 8.584 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Cd-108.
     Figures of cross sections, Cd-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
     Cd-108 (Z= 48, A=108), MT=  2 (Elastic scattering)
     Cd-108 (Z= 48, A=108), MT=  4 (Inelastic scattering)
     Cd-110 (Z= 48, A=110), MT= 17 (n,3n)
     Sn-112 (Z= 50, 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)
    -----------------------------------------------------------
     Cd-108   Pu-239   Fast      1.409780e-14   9.022540e-15 
     Cd-108   Pu-239   High      1.270820e-10   8.133270e-11 
    -----------------------------------------------------------
    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-108    U-235   High      3.386520e-11   2.167370e-11 
     Cd-108    U-238   High      1.459720e-13   9.342210e-14 
     Cd-108   Pu-239   Thermal   1.454630e-10   9.309660e-11 
     Cd-108   Pu-239   Fast      2.432590e-10   1.556860e-10 
     Cd-108   Pu-239   High      7.344870e-08   4.700720e-08 
     Cd-108   Pu-241   Thermal   1.122810e-12   7.185960e-13 
     Cd-108   Pu-241   Fast      8.049720e-12   5.151820e-12 
    -----------------------------------------------------------
    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