KUR core conversion - Neutronics calculations

As one of possible future programs for the Kyoto University Research Reactor (KUR), the Research Reactor Institute of Kyoto University (KURRI) has a plan for core conversion to the use of low-enriched uranium (LEU) fuel. A feasibility study for this started in November, 1983, as part of the joint study between KURRI and Argonne National Laboratory (ANL). Thermal-hydraulic analysis on the use of LEU fuels in the KUR was performed in 1984. The results indicated that core thermal-hydraulics posed no significant difficulties for the core conversion. During 1985, neutronics feasibility of the KUR core conversion was studied using the neutronics code (EPRI-CELL) system at ANL. This paper presents some of the results obtained from the calculations, including the comparison between the current highly enriched uranium HEU (93%, UAl-alloy, 0.586g U/cm3) and LEU (19.75%, U3Si2-Al, 3.2g U/cm3) as follows: 1. Critical mass 2. Neutron flux distribution 3. Flux peaking factor. (author)