64-Gd-172



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)
    -----------------------------------------------------------
     Gd-172    U-235   Thermal   1.120180e-17   8.961410e-18 
     Gd-172    U-235   Fast      2.692070e-16   2.153650e-16 
     Gd-172    U-235   High      9.823470e-14   6.287020e-14 
     Gd-172    U-238   Fast      8.126290e-11   5.200830e-11 
     Gd-172    U-238   High      8.087170e-11   5.175790e-11 
     Gd-172   Pu-239   Thermal   3.656500e-16   2.925200e-16 
     Gd-172   Pu-239   Fast      1.917320e-15   1.533860e-15 
     Gd-172   Pu-239   High      1.097440e-14   8.779500e-15 
     Gd-172   Pu-241   Thermal   5.850810e-14   3.744520e-14 
     Gd-172   Pu-241   Fast      1.758640e-13   1.125520e-13 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Gd-172    U-235   Thermal   1.120180e-17   8.961410e-18 
     Gd-172    U-235   Fast      2.692070e-16   2.153650e-16 
     Gd-172    U-235   High      9.823470e-14   6.277710e-14 
     Gd-172    U-238   Fast      8.126290e-11   5.200820e-11 
     Gd-172    U-238   High      8.087170e-11   5.171220e-11 
     Gd-172   Pu-239   Thermal   3.656500e-16   2.925200e-16 
     Gd-172   Pu-239   Fast      1.917320e-15   1.533860e-15 
     Gd-172   Pu-239   High      1.097440e-14   8.779500e-15 
     Gd-172   Pu-241   Thermal   5.850810e-14   3.744000e-14 
     Gd-172   Pu-241   Fast      1.758640e-13   1.125530e-13 
    -----------------------------------------------------------
    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