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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.
Frédéric Ben Saïd, Benoît Reneaume, Christophe Dauteuil, Olivier Breton, Ronan Botrel, Cédric Chicanne, Isabelle Geoffray, Rémy Collier, Olivier Legaie
Fusion Science and Technology | Volume 59 | Number 1 | January 2011 | Pages 234-239
Technical Paper | Nineteenth Target Fabrication Meeting | doi.org/10.13182/FST11-A11530
Articles are hosted by Taylor and Francis Online.
The High Power laser Energy Research facility (HiPER) is a European project dedicated to demonstrating the feasibility of producing energy by laser-driven inertial confinement fusion. A first design of the fast ignition cryogenic target has been established. It is composed of a thin-walled microshell with an inserted gold cone and filled with deuterium-tritium (DT) fuel by means of a capillary (conically guided capsule). After assembly, targets must be tight at cryogenic temperatures (16 to 19.6 K).In order to evaluate the manufacturing feasibility of a single-shot target prototype, a program has been adapted from the Laser Mégajoule (LMJ) cryogenic target fabrication know-how. Target component study for HiPER concerns a hollow gold cone (25-deg half-angle and [approximately]25-m thickness), a thin polymeric microshell (2-mm diameter and 3- to 10-m thickness), and a silica capillary (30-m outer diameter).First gas-tight targets at 77 K have been produced (helium gas leak rate [approximately]1.4 × 10-11 Pam3/s). Major efforts have been focused on thin-walled microshells, robust gold cone fabrication, and target assembly (minimizing of the glue quantity as well as helium gas leak tests) and will be discussed in this paper.