25-Mn-73



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- 73    U-235   Thermal   6.400970e-19   4.096630e-19 
     Mn- 73    U-235   Fast      1.249920e-17   7.999480e-18 
     Mn- 73    U-235   High      1.646170e-13   1.053550e-13 
     Mn- 73    U-238   Fast      3.915100e-16   2.505670e-16 
     Mn- 73    U-238   High      2.968040e-14   1.899540e-14 
     Mn- 73   Pu-241   Fast      1.407020e-17   9.004970e-18 
    -----------------------------------------------------------
    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- 73    U-235   Thermal   6.400970e-19   4.096630e-19 
     Mn- 73    U-235   Fast      1.249920e-17   7.999480e-18 
     Mn- 73    U-235   High      1.646170e-13   1.051990e-13 
     Mn- 73    U-238   Fast      3.915100e-16   2.504750e-16 
     Mn- 73    U-238   High      2.968040e-14   1.897480e-14 
     Mn- 73   Pu-241   Fast      1.407020e-17   9.004970e-18 
    -----------------------------------------------------------
    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