A Novel in-situ Raman Spectroscopy Corrosion Facility: Oxide Development on 304L Stainless Steel in High Temperature Oxygenated Solutions

Abstract

For CANDU nuclear power systems, it is of interest to assess the long-term performance of the Calandria 304L stainless steel vessel under the synergistic effect of irradiation and corrosion in the 80°C aqueous solution containing impurities. A novel facility is described consisting of a high temperature and pressure corrosion loop coupled with in-situ Raman spectroscopy and in-situ proton irradiation to examine material behaviour in more realistic reactor conditions. The in-situ Raman and corrosion loop of the facility have been evaluated prior to proton irradiation experiments. 304L stainless steel was the candidate material and experiments were conducted at 80°C and 200°C. Results reported indicate that the in-situ Raman was successful at detecting changes in the metal oxide chemistry with time and provides a feasible pathway for oxidation kinetic studies. Future work will incorporate proton irradiation, electrochemistry, effects of dissolved oxygen and hydrogen, and possibly chloride environments, along with the exploration of other nuclear-relevant candidate materials such as Zr and Fe-Cr-Al.