61-Pm-165



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)
    -----------------------------------------------------------
     Pm-165    U-235   Thermal   3.235140e-16   2.588110e-16 
     Pm-165    U-235   Fast      9.398450e-15   7.518760e-15 
     Pm-165    U-235   High      1.682310e-13   1.076680e-13 
     Pm-165    U-238   Fast      3.541140e-11   2.266330e-11 
     Pm-165    U-238   High      2.332070e-10   1.492530e-10 
     Pm-165   Pu-239   Thermal   2.219650e-14   1.420570e-14 
     Pm-165   Pu-239   Fast      5.049180e-14   3.231470e-14 
     Pm-165   Pu-239   High      1.681090e-14   1.075900e-14 
     Pm-165   Pu-241   Thermal   1.410180e-14   9.025140e-15 
     Pm-165   Pu-241   Fast      4.696260e-12   3.005600e-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)
    -----------------------------------------------------------
     Pm-165    U-235   Thermal   3.235140e-16   2.588110e-16 
     Pm-165    U-235   Fast      9.398450e-15   7.518760e-15 
     Pm-165    U-235   High      1.682310e-13   1.075080e-13 
     Pm-165    U-238   Fast      3.541140e-11   2.265610e-11 
     Pm-165    U-238   High      2.332070e-10   1.491210e-10 
     Pm-165   Pu-239   Thermal   2.219650e-14   1.420570e-14 
     Pm-165   Pu-239   Fast      5.049180e-14   3.231470e-14 
     Pm-165   Pu-239   High      1.681090e-14   1.075200e-14 
     Pm-165   Pu-241   Thermal   1.410180e-14   9.023990e-15 
     Pm-165   Pu-241   Fast      4.696260e-12   3.005610e-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