3. DESCRIPTION OF PROBLEM OR FUNCTION
The code EVGRP has been written to process the ENDF/B photonic production data. It may be used to: 1) generate, for a given set of materials and gamma producing reactions, the photo-production cross section for each reaction.
2) Calculate, for a material or a mixture of materials: the neutron- gamma group photo-production cross sections for a given reaction set; for each neutron group, the mean number of photons produced, in each gamma group, by a neutron interaction inducing the given photo- production reactions and the other possible reactions; for each neutron group, the photon mean number produced, in each gamma group, by any neutron interaction with the target; for each neutron group, the relative abundance, in the corresponding gamma group, of each produced gamma ray.