57-La-156



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)
    -----------------------------------------------------------
     La-156    U-235   Thermal   4.867410e-15   3.115150e-15 
     La-156    U-235   Fast      4.608630e-14   2.949520e-14 
     La-156    U-238   Fast      4.522540e-10   2.894430e-10 
     La-156    U-238   High      4.765010e-11   3.049610e-11 
     La-156   Pu-239   Thermal   4.897360e-14   3.134310e-14 
     La-156   Pu-239   Fast      3.169320e-14   2.028370e-14 
     La-156   Pu-241   Thermal   1.788570e-12   1.144690e-12 
     La-156   Pu-241   Fast      9.073270e-13   5.806890e-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)
    -----------------------------------------------------------
     La-156    U-235   Thermal   4.867410e-15   3.115150e-15 
     La-156    U-235   Fast      4.608630e-14   2.949520e-14 
     La-156    U-238   Fast      4.522540e-10   2.893530e-10 
     La-156    U-238   High      4.765010e-11   3.046300e-11 
     La-156   Pu-239   Thermal   4.897360e-14   3.134310e-14 
     La-156   Pu-239   Fast      3.169320e-14   2.028370e-14 
     La-156   Pu-241   Thermal   1.788570e-12   1.144500e-12 
     La-156   Pu-241   Fast      9.073270e-13   5.806890e-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