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Research interests are focussed on understanding of the mechanisms controlling the degradation of reactor structural components. This necessitates developing an understanding of processes occurring at the atomic scale, as frequently, there is a direct link between mechanisms occurring on this scale and the macroscopic performance of reactor plant components. The primary areas of interest are; Reactor Pressure Vessel embrittlement, environmentally assisted corrosion in reactor core components, irradiation and thermal ageing effects in Zr alloys employed in nuclear applications, and irradiation effects in reactor graphite.

Also see a full listing of New projects available within the Department of Materials.