Understanding Radiation Damage in Zircaloy-4 for Current and Future Nuclear Applications

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Zircaloy-4 is a Zr-based alloy of major importance for nuclear fuel cladding in pressurised water reactors. Under irradiation at high temperatures, it develops microstructural defects including dislocation loops and gas bubbles. Hydrides can also develop due to aqueous corrosion. Such defects can have significant effects on the performance of the material and hence needs to be accurately quantified for the continued use and future development of reactor technologies incorporating such alloys into their design. This PhD project will support a fledging collaboration with Rolls Royce (who will provide Zircaloy-4 samples) which has emerged from the Horizon 2020 "IL TROVATORE" project.