Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water

Effect of irradiation on corrosion of 304 nuclear grade stainless steel (304NG SS) in simulated primary water of pressurized water reactor was investigated. The investigation was conducted by comparing the microstructure of the oxide scale formed on the steel irradiated to different doses by proton. The results revealed that increasing irradiation dose promoted both the corrosion and intergranular corrosion of 304NG SS. This is attributed to the irradiation induced defects as well as the Cr depletion at the grain boundary in the steel.