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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
X. R. Wang, S. Malang, M. S. Tillack, ARIES Team
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 308-312
In-Vessel Components - FW, Blanket, Shield & VV | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12371
Articles are hosted by Taylor and Francis Online.
In this paper, the innovative FW armor design concept is presented. The “Design by Analysis” rather than “Design by Code” method as allowed by ASME for such high temperature components is used in this study. Incremental cyclic elasto-plastic analysis of considering the FW fabrication steps as well as for normal and transient operating modes is performed, accounting for stress relaxation by plastic deformations during a large number of temperature cycles. The resulting maximum strains are summarized.