Abstract
Safety-related calculations were performed using lattice code Winfrith Improved Multigroup Scheme (WIMS) and diffusion code CITATION for Ghana Research Reactor-1 (GHARR-1) core with high-enriched uranium (HEU) fuel elements. Results are provided for power peaking factors with partially inserted control rods, kinet-ic parameters and isothermal reactivity coefficients. Comparisons of some computed values with results obtain-ed using other codes, which are in good agreement, are presented Journal of Applied Science and Technology (JAST) , Vol. 5, Nos. 1 & 2, 2000, pp. 32 - 38
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