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

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