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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Late News Poster Session
Presentation Title O-23: Oxidation Studies of UN/UB2
Author(s) Megan Pritchard, Joel Turner, Timothy Abram
On-Site Speaker (Planned) Megan Pritchard
Abstract Scope Accident tolerant fuels (ATF) have the potential to enhance safety and lower costs in nuclear power stations by removing the need for safety systems and potentially providing inherent safety. It may be possible to offset increased cladding costs by creating a fuel material that contains more uranium per unit volume, reducing the required enrichment or extending fuel life. Currently there are challenges facing promising fuel materials for light water reactors (LWR) due to their reaction with high temperature steam. This project will explore the effect of light element concentration within UN on its steam reaction. A composite UN fuel also containing UB2 will be manufactured - UB2 appears to improve the hydrolysis behaviour of UN when co-sintered. Characterisation of the composite pellets will be performed alongside steam testing, to understand the effects of UB2 on UN sintering behaviour and oxidation performance.
Proceedings Inclusion? Undecided
Keywords Other, Nuclear Materials, Composites

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