Nuclear safety-related calculations for Ghana Research Reactor -1 core

  • E.H.K. Akaho Department of Nuclear Engineering & Material Science, National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG80, Legon-Accra, Ghana.
  • B.T. Maakuu Department of Nuclear Engineering & Material Science, National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG80, Legon-Accra, Ghana.

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
Published
2004-05-17
Section
Articles

Journal Identifiers


eISSN: 0855-2215