Calculation of burnup fuel cell uranium metallic with carbon dioxide cooled

Abstract

Abstract This article presents the calculation of uranium metallic fuel cell (U-10%Zr) to be used in carbon dioxide cooled Gas-cooled Fast Reactor (GFR). This fuel cell is a cylindrical cell with a 1.4 cm diameter. The fuel cell is tested without enrichment and enrichment of 1-10%. Calculation of fuel cells based on neutron transport equation using SRAC. The calculation parameter observed is the value of infinite multiplication factor (K-inf), conversion ratio, and Pu-239 atomic density. The results of the fuel cell calculation with 6% enrichment showed the K-inf and conversion ratio is relatively stable during burn-up history. While the largest atomic density of Pu-239 occurs in fuel cells without enrichment because U-238 atoms undergoing transmutation to Pu-239.