Fuel burnup calculation for HEU and LEU cores of Ghana MNSR

摘要

This study presents results of fuel burnup calculations for both HEU and LEU cores. A fuel depletion analysis of the CHARR-1 core was performed, an inventory of the actinides formed as a result of burnup was provided and then an estimation of the effect of the production of plutonium isotopes with burnup on reactor operation was made. A FORTRAN 95 code was written based on the three group model approach to represent the fast, resonance and slow neutron reactions. The results obtained for the HEU were in good agreement with literature and this study is considered a reliable tool which can estimate results of a potential LEU fuel for core conversion from HEU to LEU core.