3. DESCRIPTION OF PROGRAM OR FUNCTION
Based on a new semi-classical theory of multi-step nuclear reaction processes the code UNF code has been developed for calculations of fast neutron data for structural materials with neutron energies below 20 MeV. Besides the elastic scattering channel the code may handle decay sequences up to the (n,3n) reaction, including 14 reaction channels.
The energy spectra and double differential cross sections of all kinds of emitted particles as well as of the recoil nuclei can be obtained, Gamma production data, KERMAX factors and production spectra of n, p, alpha, deuteron, triton, helium-3 are also given. The output form is in the ENDF-6 format.