I am currently simulating the interaction of fast neutrons (energy approximately 0.5 MeV to 15 MeV) in different materials such as Aluminium, Copper, Iron, Paraffin,…
In my physics list, I am using the high precision neutron package (G4NeutronHP). The Geant4 version is 10.5. The neutron data comes from the G4NDL4.5 data files.
My question is now: Which ENDF libraries are “used” for these data files? I am asking because I noticed that for iron, the neutron interaction cross sections listed in different libraries can differ significantly (see attached plot for the isotope Fe-57. The plot shows the total cross section as a function of neutron energy retrieved from 4 different libraries). Also, I would like to know if and how I can use other ENDF libraries as data files for Geant4?
A last question: For some isotopes, the ENDF libraries contain uncertainties on the stored quantities such as the cross section. Are these uncertainties considered in Geant4?
Thanks in advance for your help!
(I am new to the forum so I hope everything is all right with this post.)