Abstract
The thermal fatigue testing of a prototypical first wall mock-up is described and a comparison is made between the experimental results and numerical calculations. The ASME-III and RCC-MR nuclear standards are applied to assess possible extensions to the design of the fusion reactor first wall as far as cyclic thermal loads are concerned.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Disclaimer: 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.