Tritium Retention in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and TFTR-Reference-Cited by-同舟云学术

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Tritium Retention in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and TFTR

Published:2005-08 Issue:1 Volume:48 Page:577-580
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Tanabe T.¹,Sugiyama K.¹,Skinner C. H.²,Bekris N.³,Gentile C. A.²,Coad J. P.⁴

Affiliation:

1. Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan

2. Princeton Plasma Physics Laboratory, P.O.Box 451, Princeton, NJ 08543, USA

3. Tritium Laboratory, Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany

4. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon Oxon, OX14 3DB, UK

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-A991

Reference13 articles.

1. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

2. Tritium Removal from Carbon Plasma Facing Components

3. Deposition of carbon, deuterium, and metals on the wall and limiters of the Tokamak Fusion Test Reactor

4. Carbon deposition in the gaps between tiles: Data from the Tokamak Fusion Test Reactor and laboratory simulation studies

5. Measurement of Tritium Surface Distribution on TFTR Bumper Limiter Tiles

Cited by 15 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. Numerical Survey of the Sponge Mechanism for Reducing Tritium Retention in Fusion Reactors;Fusion Science and Technology;2024-04

2. Erosion and Deposition, and Their Influences on Plasma Behavior (Material Transport in Tokamak);Plasma-Material Interactions in a Controlled Fusion Reactor;2021

3. Fusion—Reactor Materials;Encyclopedia of Nuclear Energy;2021

4. Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps;Chinese Physics B;2014-11

5. Hydrogen Isotopes Retention in Gaps at the JT-60U First Wall Tiles;Fusion Science and Technology;2013-05

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