Abstract
The Canadian supercritical water-cooled reactor (SCWR) is currently being designed by Canadian Nuclear Laboratories. It presents challenges to many scientists and engineers owing to the harsh environment in which the reactor must operate and the lack of knowledge in material’s performance under high temperature, pressure, and irradiation. In this study, 2 superalloys, A286 and Alloy 625, were tested in supercritical, high-pressure, and low-pressure steam at 625 °C for 1000 h; each represents a pressure of 29 MPa (SCW), 8 MPa (high-pressure steam), and finally 0.1 MPa (low-pressure steam). Results from this study show a higher oxidation rate, in terms of weight gain, for A286 under all conditions primarily due to its low Cr content. Alloy 625, on the other hand, exhibits much more oxidation resistance under all conditions due to the formation of protective Cr-containing surface oxide(s). Weight changes of A286 and Alloy 625 in supercritical water and low pressure steam are comparable, while high pressure s...
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
