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
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.