Enhancement of hydrogen isotope retention capacity for the impurity deposited tungsten by long-term plasma exposure in LHD-Reference-Cited by-同舟云学术

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Enhancement of hydrogen isotope retention capacity for the impurity deposited tungsten by long-term plasma exposure in LHD

Published:2013-10 Issue:9-10 Volume:88 Page:1699-1703
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Oya Yasuhisa,Masuzaki Suguru,Tokitani Masayuki,Yoshida Naoaki,Watanabe Hideo,Yamauchi Yuji,Hino Tomoaki,Miyamoto Mitsutaka,Hatano Yuji,Okuno Kenji

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference11 articles.

1. Tungsten as material for plasma-facing components in fusion devices

2. Recent progress of tungsten R&D for fusion application in Japan

3. Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten

4. First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE

5. The deuterium depth profile in neutron-irradiated tungsten exposed to plasma

Cited by 13 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. Temperature dependence of surface microstructure of 316 L stainless steel exposed to low-energy hydrogen ion irradiation;Fusion Engineering and Design;2023-11

2. Evaluation of hydrogen retention behavior for damaged tungsten exposed to hydrogen plasma at QUEST with high temperature wall;Fusion Engineering and Design;2022-03

3. Microstructure and Properties of Brazed W-W Joints by Ti-35Ni Alloy;Journal of Materials Engineering and Performance;2022-02-28

4. Evaluation of hydrogen retention behavior in tungsten exposed to hydrogen plasma in QUEST;Nuclear Materials and Energy;2021-03

5. Tritium removal from the LHD first-wall by the hydrogen plasma discharge;Fusion Engineering and Design;2020-10

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