Neutronics Analysis of Ghana Research Reactor-1 Low Enriched Uranium Core Using MCNP5 Code

Abstract

The neutronic and kinetic analysis of Ghana Research Reactor-1 (GHARR-1) low enriched uranium (LEU) core was carried out using MCNP5 transport code. The changes in the fuel enrichment from 12.5 % to 13.0 % and some components such as the type of fuel, cladding material which have direct influence on the neutronic parameters, require re-evaluation of the neutronic safety analysis of the reactor. The analysis include reactivity, delayed neutron fraction, control rod worth, moderator coefficient of reactivity and the neutron flux distribution in the inner and outer experimental channels at half power (17 kW) and full power (34 kW). The configuration with 335 fuel pins gave the excess reactivity of 4.03 mk which is comparable to the high enriched uranium (HEU) core. The results also revealed that, the neutron flux distribution in the inner irradiation channels are also comparable to the flux distribution of the high enriched uranium (HEU) core. Based on the results presented in this study, it can be concluded that the safety analysis of Ghana Research Reactor-1 LEU core is good and reliable replacement for the HEU core.