In the chemical and power generation industry, corrosion-resistant, austenitic stainless steels are widely used as construction materials for piping, vessels and other structural components which enclose or come into contact with aggressive or mild environments and are subjected to relevant sustained mechanical loads. Intergranular stress corrosion cracking (SCC) in these materials is therefore a common phenomenon, in particular, if the material is in a susceptible condition (e.g. sensitisation, cold work, etc.). In the nuclear industry, intergranular SCC incidents have occurred in both boiling water (BWR) and pressurised water reactors (PWR) in a wide range of stainless steel and nickel-base alloy components such as reactor internals, (reactor) pressure vessel penetrations and nozzles, main coolant piping and heat exchanger tubing [1–3]. These SCC incidents have significantly affected plant availability/economics and, in some cases, have compromised the integrity of the primary circuit and thus plant safety.