Assessing the Corrosion of Proton-Irradiated and Cold-Worked Stainless Steel 304L in Water at 300°C Via In-Situ Raman Spectroscopy

Abstract

A facility consisting of a high temperature and pressure corrosion loop coupled with in-situ Raman spectroscopy and proton irradiation has been commissioned to examine the behaviour of nuclear power plant materials under realistic environment-irradiation conditions. The oxide development on as-received, cold-worked and proton-irradiated SS 304L in water at 300°C was investigated via in-situ Raman spectroscopy over a 48-hour period; chemical and semi-quantitative kinetic information were obtained. The as-received and 0.1 dpa SS displayed similar oxidation kinetics and chemistry across all timespans, indicating that the damage imparted by protons was not sufficient to manifest a detectable change in the oxide. However, modifications in the spinel oxide chemistry and increased oxidation kinetics with time were observed for the 3.0 dpa and cold-worked SS.