Surface Distribution of Tritium on Graphite Tiles of Divertor Area in JT-60U-Reference-Cited by-同舟云学术

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

Published:2002-05 Issue:3P2 Volume:41 Page:877-881
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Tanabe T.¹,Miyasaka K.²,Sugiyama K.²,Masaki K.³,Kodama K.³,Miya N.³

Affiliation:

1. Center for Integrated Research in Science and Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan, +81-52-789-5157

2. Department of Nuclear Engineering, Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan +81-52-789-5158

3. Department of Fusion Facilities, Japan Atomic Energy Research Institute, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan +81-29-270-7430

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/FST02-A22710

Reference9 articles.

1. Tritium retention and clean-up in JET

2. Tritium profiles in tiles from the first wall of fusion machines and techniques for their detritiation

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

Cited by 14 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

2. Tritium Retention in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and TFTR;Fusion Science and Technology;2005-08

3. Recovery of Retained Tritium from Graphite Tile of JT-60U;Fusion Science and Technology;2005-08

4. Retention of Hydrogen Isotopes in Divertor Tiles Used in JT-60U;Fusion Science and Technology;2005-08

5. Retention characteristics of hydrogen isotopes in JT-60U;Journal of Nuclear Materials;2005-03

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