3. DESCRIPTION OF PROBLEM OR FUNCTION
The program calculates an
energy exchange matrix which describes the probability that a
neutron with energy E will produce a recoil atom with energy T in
a given material. In addition, the program can calculate the
primary recoil atom energy spectrum for a given neutron spectrum,
the damage cross section for the material, and an optimum lower
energy limit for use in comparing the relative damage in different
reactor spectra. The program accepts neutron scattering data
directly from the ENDF/B library tapes and, in the case of a
resonance nuclide, from a tape generated by the program SUPERTOG
(NESC Abstract 431).