To contribute to the design and materials selection of the Generation IV SuperCritical Water Reactors (Gen IV SCWR), a high-temperature mechanical property database of candidate alloys has been developed and creep models have been applied to predict long-term creep strength. The alloys in the database include representative ferritic/martensitic (F/M) steels, stainless steels, iron-nickel–base alloys, Ni-base alloys, and oxide dispersion strengthened (ODS) alloys with an emphasis on candidate austenitic and super-austenitic stainless steels. The mechanical properties were evaluated and examined with reference to ASME Section III Subsection NH code and the preliminary fuel cladding requirements in Canadian and Japanese conceptual SCWR designs. Traditional creep prediction models (i.e., Monkman-Grant model and Larson-Miller parameter) and the recent Wilshire-Scharning model were assessed and the constants of creep models were obtained. The predicted average maximum allowable stresses at temperatures and lifetimes of interest to Gen IV SCWR fuel cladding applications are presented.

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