Assessment of Corrosion and Stress Corrosion Cracking Results for SCWR Development: Gaps and Needs

Abstract

International efforts on materials evaluation for the development of supercritical water-cooled reactors (SCWRs) have produced a considerable amount of corrosion test data in the open literature. These data are helping guide the selection of candidate alloys for further, longer-term evaluation. As continuing research in this area advances, the gaps and limitations in the published data are being identified. These gaps can be seen in several areas, including the test environment and the severity of test condition as compared with reactor service/operating condition. While some of these gaps can be filled readily with existing capabilities, others require major investments in advanced test facilities.