Exploration of producing Uranium-232 for use as a tracer in uranium fuels

This study examines the production of ²³²U via neutron irradiation. Uranium-232 is considered for use as a tracer in nuclear fuel. However, a source of ²³²U is needed. This study examines the production of ²³²U via neutron irradiation of targets constructed out of either ²³¹Pa or ²³⁰Th in the High Flux Isotope Reactor. HFIR targets were modeled in MCNP to determine ²³²U yield in protactinium and thorium targets. Flux tallies were used inside the targets to determine the neutron flux inside each target. This flux was then used in SCALE 6.2 ORIGEN to determine the ²³²U yield, as well as the buildup of the byproduct ²³³U. Several ²³⁰Th enrichments were examined to determine how ²³²U yield is affected by ²³⁰Th enrichment, as well as the effects of the presence of ²³²Th. The buildup of ²²⁸Th and ²²⁹Th in thorium targets was also examined, as these isotopes may impact the feasibility of recycling of thorium target materials.