The production of an ENDF-6 compatible evaluated data file for cross sections of neutron induced reaction on 238-U is described. The evaluation covers a broad energy region from thermal neutrons up to fast ones. Evaluated cross sections for neutron induced reactions are preferably based on a parameterization by means of nuclear reaction theory. Different methodologies have to be applied to describe the structures in the resonance region and the more continuous properties of the cross sections in fast neutron region. ...
Thesis Advisor: Prof. Guinyun Kim