58-Ce-158



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)
    -----------------------------------------------------------
     Ce-158    U-235   Thermal   3.863850e-14   2.472860e-14 
     Ce-158    U-235   Fast      9.230940e-13   5.907800e-13 
     Ce-158    U-235   High      3.184360e-13   2.037990e-13 
     Ce-158    U-238   Fast      4.981670e-10   3.188270e-10 
     Ce-158    U-238   High      3.893450e-10   2.491810e-10 
     Ce-158   Pu-239   Thermal   1.859710e-13   1.190220e-13 
     Ce-158   Pu-239   Fast      1.299790e-13   8.318650e-14 
     Ce-158   Pu-239   High      8.155290e-14   5.219380e-14 
     Ce-158   Pu-241   Thermal   5.130710e-11   3.283650e-11 
     Ce-158   Pu-241   Fast      1.478890e-11   9.464880e-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)
    -----------------------------------------------------------
     Ce-158    U-235   Thermal   3.863850e-14   2.472860e-14 
     Ce-158    U-235   Fast      9.230940e-13   5.907810e-13 
     Ce-158    U-235   High      3.184360e-13   2.034980e-13 
     Ce-158    U-238   Fast      4.981670e-10   3.187220e-10 
     Ce-158    U-238   High      3.893450e-10   2.489610e-10 
     Ce-158   Pu-239   Thermal   1.859710e-13   1.190220e-13 
     Ce-158   Pu-239   Fast      1.299790e-13   8.318650e-14 
     Ce-158   Pu-239   High      8.155290e-14   5.216000e-14 
     Ce-158   Pu-241   Thermal   5.130710e-11   3.283200e-11 
     Ce-158   Pu-241   Fast      1.478890e-11   9.464880e-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