Determination of Nuclear Reaction Cross-sections for Neutron-Induced Reactions in Some Odd – A Nuclides

Abstract

The effect of the odd-even nature and mass of target nucleus on neutron reaction cross-sections have been investigated for the energy range of 1 – 30 MeV for neutron-induced reactions in the odd – A nuclides: ,  and  using the EXIFON code. This code which uses one global parameter set and is based on the analytical model for statistical multistep direct and multistep compound reactions, was used to calculate cross-sections for the (n, ?), (n, p), and (n, 2n) reactions. Calculations were compared with experimental data (EXFOR) and evaluated data (ENDF) from the IAEA nuclear data bank. Results show that charged particle emissions ((n, ?) and (n, p)) are the most dominant reaction channels in the light and intermediate mass nuclei considered. Results also show that the Na (n, 2n) reaction cross-section over predicted experimental and evaluated data, while the Na (n, ?) reaction agrees with experimental data and was in fair agreement with evaluated data while the Na (n, p) cross-section under predicted experimental and evaluated data. For magnesium, the (n, 2n) cross-section partially agree with evaluated cross-section, while the (n, ?) and (n, p) cross-sections under predicted evaluated data. And for aluminium, the calculated (n, 2n) cross-section over predicted experimental and evaluated data, the (n, ?) data fairly reproduced experimental and evaluated cross-sections while the (n, p) reaction cross-section was in fair agreement with experimental and evaluated data. The explanations for the discrepancies and trends observed have been given.

Keywords: Nuclear reaction cross-section, Neutron-induced reaction, nuclear data, EXIFON code