My research focuses on understanding and predicting the deformation, environmental degradation and failure of structural materials in light water reactors (LWRs), high-temperature gas-cooled reactors (HTGRs) and fusion reactors. I aim to link microstructure, chemistry and surface condition to material performance during service and decommissioning.

• Nuclear materials: Zirconium alloys and steels under combined irradiation, mechanical loading and corrosive environments.
• Hydrogen effects: Hydrogen (H, D and T) and hydride-assisted degradation in zirconium alloys and steels, including austenitic, duplex, RAFM and additively manufactured alloys.
• Advanced characterisation: Electron microscopy, EBSD, TKD, NanoSIMS, neutron diffraction and synchrotron X-ray techniques to quantify microstructure, chemistry, deformation and residual stress.
• Gen IV reactors: High-temperature alloys, including Alloy 800H/HT, Hastelloy X/XR and Alloy 617, with a focus on creep, environmental degradation in impure helium, irradiation effects and decommissioning.
• Safeguards and non-proliferation: Tritium transport, nuclear safeguards, non-proliferation and export control.