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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. Ueki, M. Hirabayashi, T. Kunugi, T. Yokomine, K. Ara
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 846-850
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST56-846
Articles are hosted by Taylor and Francis Online.
In a lead-lithium (Pb-17Li) liquid metal blanket concept, Pb-17Li eutectic alloy circulates both as breeder and coolant under a strong plasma-confining magnetic field, experiencing magneto-hydro-dynamic (MHD) force: Lorentz force. An important aspect of the bilateral US/Japan collaboration on Tritium, Irradiations, and Thermofluid for America and Nippon (TITAN) is to investigate tritium behavior and thermal control in the Pb-17Li eutectic alloy, flow and heat transfer characterizations, and mitigation of MHD effects. The present paper focuses on Ultrasonic Doppler Velocimetry (UDV) as an effective diagnostic to measure the Pb-17Li flow in the presence of the strong magnetic field. This paper firstly describes a favorable wetting material for high-temperature transducer. Next, the acoustic property database of Pb-17Li eutectic alloy is presented. Finally, material analyses after high temperature measurements are performed to discuss the durability of titanium transducer.