Recovery of Retained Tritium from Graphite Tile of JT-60U-Reference-Cited by-同舟云学术

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Recovery of Retained Tritium from Graphite Tile of JT-60U

Published:2005-08 Issue:1 Volume:48 Page:565-568
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Takeishi Toshiharu¹,Katayama Kazunari¹,Nishikawa Masabumi¹,Miya Naoyuki²,Masaki Kei²

Affiliation:

1. Department of Applied Quantum Physics and Nuclear Engineering, Graduate School of Engineering, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581, Japan

2. Naka Fusion Research Establishment, Japan Atomic Energy Research Institute 801-1 Mukouyama, Naka-machi, Naka-gun, Ibaraki, 311-0193, Japan

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/FST05-A988

Reference12 articles.

1. In-vessel tritium retention and removal in ITER

2. Tritium depth profiles in graphite and carbon fibre composite material exposed to tokamak plasmas

3. Imaging plate technique for determination of tritium distribution on graphite tiles of JT-60U

4. Surface Distribution of Tritium on Graphite Tiles of Divertor Area in JT-60U

5. Tritium distribution in JT-60U W-shaped divertor

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Tritium release from bulk of carbon-based tiles used in JT-60U;Journal of Nuclear Materials;2006-03

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