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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.
S. W. Haan, M. C. Herrmann, P. A. Amendt, D. A. Callahan, T. R. Dittrich, M. J. Edwards, O. S. Jones, M. M. Marinak, D. H. Munro, S. M. Pollaine, J. D. Salmonson, B. K. Spears, L. J. Suter
Fusion Science and Technology | Volume 49 | Number 4 | May 2006 | Pages 553-557
Technical Paper | Target Fabrication | doi.org/10.13182/FST49-553
Articles are hosted by Taylor and Francis Online.
Targets intended to produce ignition on NIF are being simulated and the simulations are used to set specifications for target fabrication. Recent design work has focused on designs that assume only 1.0 MJ of laser energy instead of the previous 1.6 MJ. To perform with less laser energy, the hohlraum has been redesigned to be more efficient than previously, and the capsules are slightly smaller. The main-line hohlraum design now has a SiO2 foam fill, a wall of U-Dy-Au, and shields mounted between the capsule and the laser entrance holes. Two capsule designs are being considered. One has a layered Cu-doped Be ablator, and the other layered Ge-doped CH. Both can perform acceptably with recently demonstrated ice layer quality, and with recently demonstrated outer surface roughness. Smoothness of the internal interfaces may be an issue for the Be(Cu) design, and it may be necessary either to polish partially coated shells or to improve process control so that the internal layers are smoother. Complete tables of specifications are being prepared for both targets, to be completed this fiscal year. All the specifications are being rolled together into an error budget indicating adequate margin for ignition with the new designs.