My research focuses on understanding and predicting the deformation, environmental degradation and failure of structural materials in light water reactors (LWR), high-temperature gas-cooled reactors (HTGR) and fusion reactors, linking microstructure and surface state to performance in service and during decommissioning.

• Nuclear materials: Zirconium alloys and steels under combined irradiation, loading and corrosive environments.

• Hydrogen effects: Hydrogen- (H, D or T) and hydride-assisted degradation in zirconium alloys and steels, including austenitic, duplex, RAFM and additively manufactured variants.

• Advanced characterisation: Electron microscopy, EBSD, TKD, NanoSIMS, neutron diffraction and synchrotron X-ray techniques to quantify microstructure, chemistry and stress.

• Gen IV reactors: Alloy 800H(T), Hastelloy X(R) and Alloy 617 in impure helium, creep, environmental degradation with irradiation assistance, and decommissioning.

• Non-proliferation: Tritium transportation, safeguards, non-proliferation and export control.