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

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

Lu Wang, Hai-Shan Zhou, Hao-Dong Liu, Qiang Qi, Han-Jun Tu, Li-Qun Shi, Guang-Nan Luo2022年被引用 1Nuclear FusionIF 3出版社

The effect of helium (He)-induced surface microstructure on deuterium (D) plasma-driven permeation through a reduced activation ferritic/martensitic steel CLF-1 has been studied. CLF-1 steel was pre-exposed by He plasma with ion fluence of 1022–1024 He m−2 and an incident energy of 100 eV at 708 K. The following D plasma-driven permeation experiment was performed at 693 K. Steady-state D permeation flux decreases with the increase in He ion fluence. D diffusion coefficient is not significantly affected by He pre-damage, while D reflection coefficient increases with the enhancement of He ion fluence. Scanning electron microscope and transmission electron microscope analyses clearly reveal the evolution of surface roughness and He bubble layer after He plasma exposure. Elastic recoil detection was used to identify He concentration depth profiles in the samples. Both the surface microstructure modification and He bubble layer formation contribute to the reduction of D permeation.

日本語訳

ヘリウム(He)誘起表面微細構造が重水素(D)プラズマ駆動透過に及ぼす影響を、フェライト系/マルテンサイト系鋼CLF-1において研究した。CLF-1鋼を、イオンフルエンス1022~1024 He m⁻²、入射エネルギー100 eV、温度708 KのHeプラズマに事前曝露した。続いて、重水素プラズマ駆動透過実験を693 Kで実施した。定常状態のD透過フラックスは、Heイオンフルエンスの増加とともに減少した。D拡散係数はHe事前損傷によって有意な影響を受けなかったが、D再放出係数はHeイオンフルエンスの増加とともに増大した。走査型電子顕微鏡および透過型電子顕微鏡分析により、Heプラズマ曝露後の表面粗さとHeバブル層の明瞭な発達が明らかになった。弾性反跳検出法を用いて、試料中のHe濃度深さ分布を同定した。表面微細構造の改変とHeバブル層の形成の両方が、D透過の低減に寄与することが示された。

wiki

Reduced activation ferritic/martensitic steel
この論文にはまだAI要約がありません。

関連論文

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

2023Nuclear Fusion

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

2022Nuclear Fusion

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

2025Nuclear Fusion

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

2019Nuclear Fusion

Mixed hydrogen isotopes plasma-driven permeation through CLF-1 RAFM steel for ITER HCCB TBM

2022Nuclear Fusion

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

2026Nuclear Fusion

Hydrogen isotope transport across tungsten surfaces exposed to a fusion relevant He ion fluence

2017Nuclear Fusion

Deuterium retention in recrystallized tungsten exposed to high-flux plasma with fluences up to 1 × 1029 m−2

2025Nuclear Fusion

Exposure of Indian RAFM under variation of He+ flux and target temperature in the CIMPLE-PSI linear device

2020Nuclear Fusion

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

2020Nuclear Fusion