Effect of Heating Temperature on Deuterium Retention Behavior for Helium/Carbon Implanted Tungsten-Reference-Cited by-同舟云学术

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Effect of Heating Temperature on Deuterium Retention Behavior for Helium/Carbon Implanted Tungsten

Published:2015-10 Issue:3 Volume:68 Page:531-534
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Sato Misaki¹,Yuyama Kenta¹,Li Xiao-Chun¹,Ashikawa Naoko²,Sagara Akio²,Yoshida Naoaki³,Chikada Takumi¹,Oya Yasuhisa¹

Affiliation:

1. Graduate School of Science, Shizuoka University, 836 Ohya, Suruga-ku, Shizuoka 422-8529, JAPAN

2. National Institute for Fusion Science, 322-6 Oroshi-cho, Toki-city, Gifu 509-5292, JAPAN

3. Research Institute for Applied Mechanics, Kyushu University, Kasuga-koen, Kasuga-city, Fukuoka 816-8580, 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/FST14-971

Reference10 articles.

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

2. Effects of tungsten surface conditions on carbon deposition

3. The effects of high fluence mixed-species (deuterium, helium, beryllium) plasma interactions with tungsten

4. Analysis of PWI footprint traces and material damage on the first walls of the spherical tokamak QUEST

5. Dynamics of hydrogen isotope trapping and detrapping for tungsten under simultaneous triple ion (C+, D2+ and He+) implantation

Cited by 10 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. In-situ TEM characterization of dislocation loops in tungsten under simultaneous helium and hydrogen irradiation;Journal of Nuclear Materials;2024-09

2. Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature;International Journal of Hydrogen Energy;2020-03

3. Research frontier of tritium for fusion reactor – toward the DEMO reactor (7);Journal of the Atomic Energy Society of Japan;2019

4. Effect of Damage Introduction and He Existence on D Retention in Tungsten by High Flux D Plasma Exposure;Recent Advances in Technology Research and Education;2018-08-19

5. Surface or bulk He existence effect on deuterium retention in Fe ion damaged W;Nuclear Materials and Energy;2018-08

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