FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

Xue-Chun Li, Hai-Shan Zhou, Hao-Dong Liu, Lu Wang, Guang-Nan Luo2022年被引用 5Nuclear FusionIF 3出版社

Experiments concerning the effect of helium (He) plasma exposure on deuterium (D) plasma-driven permeation through tungsten (W) foils in a linear plasma facility have been performed. 0.05 mm thick W foils were exposed to ∼2 × 1020 m−2 s−1 He plasma with various fluences at 883 K. After He irradiating, D permeation tests were performed for the samples and retention was also measured by high-resolution thermal desorption spectroscopy. It was observed that He pre-irradiation resulted in a significant reduction of D permeation and retention in W. Microstructure observation indicated that the surfaces of the samples after He irradiation turned rough and He nanobubbles were formed near the surface. Defective structures including He nanobubbles likely enhance D reemission and accordingly reduce the permeation and retention in He pre-irradiated W.

日本語訳

ヘリウム(He)プラズマ曝露が線形プラズマ装置におけるタングステン(W)箔の重水素(D)プラズマ駆動透過に及ぼす影響に関する実験を実施した。厚さ0.05 mmのW箔を、種々のフルエンスで約2 × 10²⁰ m⁻² s⁻¹のHeプラズマに883 Kで曝露した。He照射後、試料についてD透過試験を実施し、さらに高分解能熱脱離分光法により保持量も測定した。Heの事前照射により、WにおけるDの透過および保持が有意に低減することが観察された。微細組織観察により、He照射後の試料表面は粗くなり、表面近傍にHeナノバブルが形成されていることが示された。Heナノバブルを含む欠陥構造は、Dの再放出を促進し、それによりHe事前照射WにおけるDの透過および保持を低減すると考えられる。

この論文にはまだAI要約がありません。

関連論文

Reduced D trapping by plasma-implanted He nanobubbles in radiation damaged tungsten

2019Nuclear Fusion

Observations of suppressed retention and blistering for tungsten exposed to deuterium–helium mixture plasmas

2009Nuclear Fusion

Hydrogen isotope plasma-driven permeation through RAFM steel: isotope exchange and helium irradiation effect

2023Nuclear Fusion

The effect of He-induced surface microstructure on D plasma-driven permeation through RAFM steel

2022Nuclear Fusion

Effects of helium irradiation damage on deuterium plasma-driven permeation through tungsten coated RAFM steel

2025Nuclear Fusion

Retention and permeation properties of deuterium in tungsten under irradiation of the D–He mixture plasma

2018Fusion Engineering and Design

Deuterium transport and retention in the bulk of tungsten containing helium: the effect of helium concentration and microstructure

2020Nuclear Fusion

Effect of fuzz and He bubble on deuterium transport behavior through tungsten

2026Nuclear Fusion

In situ study of short-term retention of deuterium in tungsten during and after plasma exposure in PSI-2

2021Nuclear Fusion

Deuterium retention in tungsten under the combined influence of displacement damage and helium

2025Nuclear Fusion