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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.
E. T. Alger, E. G. Dzenitis, E. R. Mapoles, J. L. Klingmann, S. D. Bhandarkar, J. G. Reynolds, J. W. Florio, D. M. Lord, C. Castro, K. Segraves
Fusion Science and Technology | Volume 55 | Number 3 | April 2009 | Pages 269-275
Technical Paper | Eighteenth Target Fabrication Specialists' Meeting | doi.org/10.13182/FST08-3506
Articles are hosted by Taylor and Francis Online.
Inertial confinement fusion ignition experiments in the National Ignition Facility require a capsule containing deuterium-tritium fuel at cryogenic temperatures. To better understand how to produce and control the required uniform fuel ice layer, experimental layering targets are fabricated and assembled to be dimensionally similar to the ignition targets and vacuum leaktight at 18 K. Low production yield of these targets demanded a more quantitative understanding of the interfacial behavior of bonded joints and required the development of more deterministic assembly methods. Each sealing joint was individually analyzed, and target components, assembly processes, and tooling were modified as needed to make robust leaktight targets. The function, design, and assembly methods of experimental layering targets are described.