|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Creep Testing of 70% Theoretical Density U10Zr
||Jake Fay, Fidelma Di Lemma, Luca Capriotti, Jie Lian
|On-Site Speaker (Planned)
Metallic uranium alloys such as U10Zr are a promising nuclear fuel type in advanced reactor designs with advantages of improved thermal conductivity and being able to operate to high burnups (>10 at%). These fuels however exhibit very different swelling behaviors compared to ceramic fuels which produces mechanical interactions between the fuel and cladding that are not fully understood. This project aims to develop a better understanding of these mechanical interactions by measuring the creep behavior of porous U10Zr. U10Zr samples will be sintered to 70% theoretical density, characteristic of the density of U10Zr fuels after initial swelling. Compressive creep testing will then be performed with and without constraint to mimic the conditions experienced at the top of the fuel column. The resulting creep parameters determined from this study will be valuable for better understanding the mechanical interactions between metallic fuel and cladding and for improving modeling capabilities for metallic fuels.
||Nuclear Materials, Mechanical Properties, Characterization