from the conferences organized by TANGER Ltd.
Among the advanced reactor designs of the fourth generation of nuclear reactors, the Lead-cooled Fast Reactor (LFR) stands out as one of six distinct types. The corrosion damage of the steels, it is caused by liquid metal acting on the structural material, which is considered a significant obstacle in the development of the fast reactors concept. The corrosion resistance and chemical compatibility with environment of 9Cr-1Mo, ferritic alloy steel (T91), in condition of the static liquid lead with 1.10-6 wt.% oxygen at 520 ºC are analysed in this study. The specimens were exposed for 3500 hours. The specimens tested were the reference T91 and T91 with the coating on base Al and Ti was applied to the second specimen. The coating applied by physical vapor deposition were used for corrosion resistance improvement. The formed oxide scale of reference T91 consists of an outer layer with a Fe-Cr spinel structure and an inner internal oxidation zone (IOZ). Corrosion damage was characterized using electron microscopy techniques, which identified networks of solution-based attack (SBA) intrusion beneath liquid lead wetted surfaces. The damage to the coating depends on their chemical composition and structure of the coating. However, in general, the application of the coating increased the resistance of the surface to corrosion damage.
Keywords: Ferritic steel, 9Cr-1Mo, coating, liquid/molten lead, lead-cooled fast reactor (LFR)© This is an open access article distributed under the Creative Commons Attribution License which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.