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Supercritical water-cooled reactor (SCWR) is an innovative Generation IV nuclear reactor. Nickel-based alloys, such as UNS N06625, UNS R20033 and UNS N07214 alloys, are selected for the fuel cladding. Knowledge gaps exist as regards their use for the fuel cladding in the SCWR. This paper introduces laboratory results on corrosion and stress corrosion cracking (SCC) of the nickel-based alloys.
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