Corrosion Behavior of Candidate Alloys for Supercritical Water Reactors

摘要: The corrosion and stress cracking behavior of metallic cladding other core internal structures is critical to the success Generation IV Supercritical Water-cooled Reactors (SCWR). eventual materials selected will be chosen based on combined corrosion, stress-corrosion, mechanical performance, radiation stability properties. Among being considered are austenitic stainless steels, ferritic/martensitic nickel-base alloys. This paper reports initial studies performance candidate alloys 316 steel, Inconel 718, Zircaloy-2, all exposed supercritical water at 300-500 deg. C in a loop University Wisconsin. Long-term AISI 347, also has been examined by sectioning samples from component that was for period about 30 years Genoa 3 Water fossil power plant located Genoa, (authors)