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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.
Y. Nakao, M. Katsube, T. Ohmura, Y. Saito, T. Johzaki, K. Mima
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 401-404
IFE Target Design | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8934
Articles are hosted by Taylor and Francis Online.
The possibility of igniting D3He plasma in the fast-ignition, inertial confinement fusion scheme is discussed. Use of a small amount of DT fuel as an igniter is indispensable in order to mitigate the requirement on driver energy. Simulations have been made for a DT/D3He fuel compressed to 2000 ~ 4000 times the liquid density. The DT igniter is placed at the edge of the compressed fuel. The work shows that it is possible to obtain sufficient pellet gains (100) with realistic driver energy below 10 MJ. The essential roles of DT fusion neutron and nuclear elastic scattering are clarified. The possibility to reduce the amount of DT fuel is discussed.