Corrosion Behavior of Candidate Alloys for Supercritical Water Reactors

Conference · Thu Jul 01 04:00:00 EDT 2004

OSTI ID:21160639

Sridharan, K; Zillmer, A; Licht, J R; Allen, T R; Anderson, M H; Tan, L ^[1]

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1. Department of Engineering Physics, University of Wisconsin, 1500 Engineering Drive, Madison, WI (United States)

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

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160639
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
AUSTENITIC STEELS
CRACKING
FERRITIC STEELS
INCONEL 718
MARTENSITIC STEELS
STRESS CORROSION
WATER
WATER COOLED REACTORS
ZIRCALOY 2