Grain boundary composition in austenitic stainless steels established by various equilibrium and nonequilibrium processes is assessed and its possible influence on intergranular stress corrosion cracking (IGSCC) in light-water reactor environments examined. Interfacial Cr concentration is
shown to be the dominant material variable promoting IGSCC of austenitic stainless steels in oxidizing high-temperature water. Cracking susceptibility is a direct function of the boundary Cr content regardless of depletion width. Small levels of depletion, 1 to 2 wt% below bulk Cr
concentrations (below -17 wt% for 304SS), are sufficient to promote IGSCC. As a result, many observations of irradiation-assisted (IA) SCC in boiling-water reactor environments are consistent with radiation-induced Cr depletion. However, grain boundary Cr depletion does not explain
IGSCC in (unsensitized) cold-worked stainless steels or IASCC of stainless steels at low electrochemical potentials (hydrogen-water chemistry). Significant interfacial enrichment of Cr, MO and perhaps B are likely in solution- and mill-annealed stainless steels which may play a role in the IGSCC of cold-worked materials and delay IASCC to higher radiation doses. Existing data indicate that impurities and minor elements which segregate to stainless steel grain boundaries do not have a direct effect on cracking susceptibility. Critical research is needed to isolate causes for IGSCC in high-strength (cold-worked and irradiated) stainless steels.