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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.
H. H. Toudeshki, C. J. Martin, F. Najmabadi, J. P. Blanchard
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 535-540
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST15-112
Articles are hosted by Taylor and Francis Online.
ARIES ACT-1 is a conceptual design for a commercial tokamak with aggressive physics and engineering. In the spirit of advanced engineering, the vacuum vessel design employed several novel concepts. It eliminates the use of water cooling in order to allow higher temperature operation and reduce the tritium inventory. It employs a low activation bainitic steel that eliminates the need for post-weld heat treatment. It includes sufficient volume to accommodate a full loss of coolant accident. Finally, it employs a novel mechanical design in order to withstand the operating stresses during normal operation, anticipated transients, and disruptions. In this paper, we present the most recent design for this component, update the stress analysis confirming the suitability of the design, and present results for disruption forces due to a plasma quench.