Tritium Distribution on First Wall Carbon Tiles in JT-60U
Author:
Affiliation:
1. Kyushu University, Kasuga, Fukuoka, Japan, 816-8580
2. Japan Atomic Energy Agency, Mukouyama 801-1, Naka-shi, Ibaraki, Japan, 311-0193
Publisher
Informa UK Limited
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST11-A12731
Reference11 articles.
1. Bulk hydrogen retention in graphite at elevated temperature
2. Deuterium retention in carbon fibre composites NB31 and N11 irradiated with low-energy D ions
3. Assessment of the heating technique as a possible ex situ detritiation method for carbon wall materials from fusion machines
4. Imaging plate technique for determination of tritium distribution on graphite tiles of JT-60U
5. Tritium profile in plasma-facing components following D–D operation
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2. Behavior of Fuels in Reactor;Tritium: Fuel of Fusion Reactors;2016-12-06
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4. Hydrogen Isotopes Retention in Gaps at the JT-60U First Wall Tiles;Fusion Science and Technology;2013-05
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