48-Cd-134



Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0 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-134    U-235   Thermal   9.315170e-13   5.961710e-13 
     Cd-134    U-235   Fast      3.013770e-12   1.928810e-12 
     Cd-134    U-235   High      2.062830e-12   1.320210e-12 
     Cd-134    U-238   Fast      9.373490e-10   5.999040e-10 
     Cd-134    U-238   High      1.081170e-10   6.919540e-11 
     Cd-134   Pu-239   Thermal   2.139660e-13   1.369380e-13 
     Cd-134   Pu-239   Fast      1.839700e-13   1.177410e-13 
     Cd-134   Pu-239   High      1.230800e-12   7.877110e-13 
     Cd-134   Pu-241   Thermal   2.620420e-12   1.677070e-12 
     Cd-134   Pu-241   Fast      4.896320e-12   3.133640e-12 
    -----------------------------------------------------------
    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-134    U-235   Thermal   9.315170e-13   5.961710e-13 
     Cd-134    U-235   Fast      3.013770e-12   1.928810e-12 
     Cd-134    U-235   High      2.062830e-12   1.318250e-12 
     Cd-134    U-238   Fast      9.373490e-10   5.996840e-10 
     Cd-134    U-238   High      1.081170e-10   6.912040e-11 
     Cd-134   Pu-239   Thermal   2.139660e-13   1.369380e-13 
     Cd-134   Pu-239   Fast      1.839700e-13   1.177410e-13 
     Cd-134   Pu-239   High      1.230800e-12   7.872000e-13 
     Cd-134   Pu-241   Thermal   2.620420e-12   1.676800e-12 
     Cd-134   Pu-241   Fast      4.896320e-12   3.133640e-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