A preliminary neutronic evaluation of the high temperature nuclear reactor (HTTR) using reprocessed fuel

作者：Sousa R V; Tanure L P A R; Costa D F; Pereira C^*; Veloso M A F; de Oliveira A H

来源：Annals of Nuclear Energy, 2014, 65: 232-238.

DOI：10.1016/j.anucene.2013.10.033

• HTTR
• Reprocessed fuel
• Criticality
• Burn-up
• Thorium

The High Temperature Engineering Test Reactor (HTTR), a 30 MWth, graphite-moderated, helium-cooled reactor constructed by the Japanese government was simulated using reprocessed fuel obtained by UREX+ and spiked with thorium-232 and with depleted uranium. The effective neutron multiplication factor and the nuclear fuel evolution during the burn-up were analyzed. This study was performed using the ORNL SCALE 6.0 code, with CSAS6 and TRITON6 control modules. The results show in a preliminary way that the burn-up of reprocessed fuels in the HTTR core is possible, although the fissile material quantities should be increased while compared with the enrichments of the standard fuel.

• 出版日期2014-3