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

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