Feasibility study on the use of low-enriched-uranium fuel in a new research reactor of high performance

A design work was performed from a view point of nuclear characteristics to examine the feasibility of using low-enriched-uranium (LEU) fuel in a new research reactor of high performance, which has a light-water moderated core with a thick heavy-water reflector. The neutronics calculation was carried out using the SRAC code system for a core loaded with LEU aluminide or silicide fuel in comparison with a core of highly-enriched-uranium (HEU) alloy fuel. The present study is focused to investigate the effects of (1) the aluminum clad thickness, (2) the use of beryllium or graphite reflector between the fuel region and the heavy-water reflector, and (3) the core height on the effective multiplication factor and the peak value of thermal neutron flux in the heavy-water reflector region. The result show that LEU fuel would be feasible in the new reactor to achieve a design goal. (author)