59-Pr-160



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)
    -----------------------------------------------------------
     Pr-160    U-235   Thermal   2.815520e-14   1.801930e-14 
     Pr-160    U-235   Fast      9.091230e-13   5.818390e-13 
     Pr-160    U-235   High      8.481620e-13   5.428240e-13 
     Pr-160    U-238   Fast      5.762150e-10   3.687770e-10 
     Pr-160    U-238   High      1.021110e-09   6.535120e-10 
     Pr-160   Pu-239   Thermal   4.759250e-13   3.045920e-13 
     Pr-160   Pu-239   Fast      3.269470e-13   2.092460e-13 
     Pr-160   Pu-239   High      3.532290e-13   2.260670e-13 
     Pr-160   Pu-241   Thermal   1.120180e-10   7.169150e-11 
     Pr-160   Pu-241   Fast      3.867090e-11   2.474940e-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)
    -----------------------------------------------------------
     Pr-160    U-235   Thermal   2.815520e-14   1.801930e-14 
     Pr-160    U-235   Fast      9.091230e-13   5.818390e-13 
     Pr-160    U-235   High      8.481620e-13   5.420200e-13 
     Pr-160    U-238   Fast      5.762760e-10   3.686420e-10 
     Pr-160    U-238   High      1.021250e-09   6.528040e-10 
     Pr-160   Pu-239   Thermal   4.759250e-13   3.045920e-13 
     Pr-160   Pu-239   Fast      3.269470e-13   2.092460e-13 
     Pr-160   Pu-239   High      3.532290e-13   2.259200e-13 
     Pr-160   Pu-241   Thermal   1.120180e-10   7.167990e-11 
     Pr-160   Pu-241   Fast      3.867090e-11   2.474940e-11 
    -----------------------------------------------------------
    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