Investigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools

Abstract Core conversion requires some evaluation of the reactor safety. Changes to reactivity worth, shutdown margin, power density and material properties are crucial proper functioning reactor. The focus this article is study neutron flux distribution in core radiation damage on candidate clads. Ghana Research Reactor-1 (GHARR-1) operates at maximum 30 kW order attain a 1.0× 10 12 n·cm –2 ·s for high enriched uranium core. Using GHARR-1 geometry, considering 348 fuel pins, multiplication factor (K eff ) calculated enrichments 10%, 12.5%, 16%, 20%, 30% 90.2%. spectrum generated 26 group also specified enrichments. ion/particle interactions with targets (clad) were studied Stopping Range Ion Matter code establish best clad based recorded defects vacancies generated. From calculations simulations, choice from clads assessment SiC. calculation campaign length gives 7.5 years. sustained by prospective showed low susceptibility swelling other forms deformation.