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Tritium Behavior in Materials Related to Nuclear Fusion Engineering
November 1, 2019 @ 11:00 am - 12:00 pm
To design a fusion reactor with tritium self-sufficiency, and for safe operation of molten salt reactors, it is essential to understand tritium chemical and mass transport behavior in the coolant and the solid structural materials. In order to operate a fusion reactor continuously, tritium must be produced in the blanket of the fusion reactor, since tritium is scarce in nature. Tritium breeding materials include lithium and beryllium. The breeding, separation and recovery of tritium in fusion reactors is important for sustainable tritium fuel production for fusion reactors. Furthermore, safe handling of tritium is essential for safety in fusion and fission systems. Tritium readily dissolves and permeates metal alloys at high temperatures, and tritium speciates in a diversity of chemical forms in high temperature liquids. Liquid LiF-BeF2 is investigated as a coolant and tritium breeding medium for fusion reactors. This talk introduces the ongoing research at Kyushu University and, more broadly, in Japan, on tritium behavior in molten salts , and on tritium behavior in graphite materials . The research plan for the development of a molten salt loop at Kyushu University will also be discussed.
Professor Kazunari Katayama is an Associate Professor of Energy Chemical Engineering in the Department of Advanced Energy Engineering Science at the Interdisciplinary Graduate School of Engineering Sciences at Kyushu University in Japan. Professor Katayama’s research focuses on Tritium behavior in Li compounds (Li2TiO3), molten salt (FLiNaBe) and natural soil, chemical reactions in supercritical CO2, and tritium production in a high temperature gas cooled reactor. Professor Katayama teaches courses on probability and statistics, process chemical engineering, and energy engineering. Professor Katayama earned a Ph. D. in engineering from Kyushu University in 2004, a M.S. in fusion engineering and tritium science and technology from Kyushu University in 2001, and a B.S. in nuclear engineering from Kyushu University in 1997.
 S. Fukada et al., “Reaction rate of beryllium with fluorine ion from Flibe redox control” Journal of nuclear materials, 367-370 (2007) 1190-1196.
 K. Katayama et al, “Release behavior of tritium from graphite material” Fusion Science and Technology, 41 (2002) 53-62.
 K. Katayama et al., “Tritium release behavior from the graphite tiles used at the dome unit of the W-shaped diverter region in JT-60U”, Journal of Nuclear Materials 340 (2005) 82-92.
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