Finite geometry and multiple scattering corrections for neutron cross section measurements

Computer programs EFFIGY and EFFIGYC have been developed to calculate finite geometry and multiple scattering corrections for fast neutron cross-section measurements. These programs employ the Monte Carlo method to simulate time-of-flight spectra of neutrons scattered by single- or multiple-element, cylindrical or annular samples illuminated by a pulsed, monoenergetic neutron source. EFFIGY calculates corrections to angular distributions of discrete neutron groups appearing in the scattering spectra for low nuclear excitation. In addition, EFFIGYC corrects the energy distribution of the ''continuum'' of neutrons produced by (n,n/prime/) reactions leading to overlapping levels, and removes a contribution to the scattering spectra due to source neutrons from other than the monoenergetic source reaction. 13 refs