25-Mn-72



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)
    -----------------------------------------------------------
     Mn- 72    U-235   Thermal   6.073650e-18   3.887140e-18 
     Mn- 72    U-235   Fast      1.188250e-16   7.604790e-17 
     Mn- 72    U-235   High      1.229360e-12   7.867950e-13 
     Mn- 72    U-238   Fast      1.945610e-15   1.245200e-15 
     Mn- 72    U-238   High      2.342120e-13   1.498960e-13 
     Mn- 72   Pu-239   Thermal   9.078030e-18   5.809950e-18 
     Mn- 72   Pu-239   Fast      1.834660e-16   1.174180e-16 
     Mn- 72   Pu-239   High      3.421060e-13   2.189480e-13 
     Mn- 72   Pu-241   Thermal   1.168000e-18   7.475190e-19 
     Mn- 72   Pu-241   Fast      1.360990e-16   8.710340e-17 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Mn- 72    U-235   Thermal   6.073650e-18   3.887140e-18 
     Mn- 72    U-235   Fast      1.188250e-16   7.604790e-17 
     Mn- 72    U-235   High      1.229360e-12   7.856300e-13 
     Mn- 72    U-238   Fast      1.945610e-15   1.244740e-15 
     Mn- 72    U-238   High      2.342120e-13   1.497330e-13 
     Mn- 72   Pu-239   Thermal   9.078030e-18   5.809950e-18 
     Mn- 72   Pu-239   Fast      1.834660e-16   1.174180e-16 
     Mn- 72   Pu-239   High      3.421060e-13   2.188060e-13 
     Mn- 72   Pu-241   Thermal   1.168000e-18   7.473980e-19 
     Mn- 72   Pu-241   Fast      1.360990e-16   8.710340e-17 
    -----------------------------------------------------------
    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