Abstract
The verification of the structural components of demonstration fusion power plants requires design criteria developed specifically for those components and the unique conditions at which they are operated. Therefore the creation of a body of structural design criteria appropriate for demonstration fusion power plants is an important activity, with particular attention required for the in-vessel components of the divertor and blanket. For posited failure modes associated with the candidate in-vessel components for the current European Demonstration Power Plant design (EU DEMO), this paper highlights the gaps identified in the leading suites of relevant structural design criteria (ASME BPVC Division III, AFCEN RCC-MRx, ITER SDC-IC). Opportunities for innovative development are then explored for these gaps. Finally, a development path for structural design criteria against the needs of EU DEMO is discussed.
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.
