Neutronic analysis of high burnup thorium-HALEU fuels in PHWR.

Recent developments have been made in a novel fuel for pressurised heavy water reactors: high burnup oxide fuels composed of a mixture of thorium and high assay low enriched uranium. Several claims are made regarding the performance of such fuels in terms of economics, waste and non-proliferation, among others. This article analyses this class of fuel using an infinite lattice study in SERPENT. First, a set of fuel compositions in the thorium/uranium enrichment design space that satisfy the high burnup target is produced. Then, a representative thorium-based fuel is compared to a uranium-only fuel with the same discharge burnup, as well as current standard fuel, in the context of the various performance claims. • A novel thorium-HALEU for use in pressurised heavy water reactors is considered. • Design space of thorium and uranium composition explored to achieve 55 MWd/kg burnup. • Claimed advantages in waste and non-proliferation are considered, as well as resource utilisation and reactor behaviour. [ABSTRACT FROM AUTHOR]