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

Fuzz nanostructure and erosion on tungsten–vanadium alloys exposed to helium plasma in the STEP linear plasma device

Jun Wang, Long Cheng, Yue Yuan, Guang-Hong Lu, Lin Ge, Zhang-Jian Zhou2019年被引用 10Nuclear FusionIF 3出版社

Tungsten–vanadium (W–V) alloys with 5 and 10 wt.% V made using hot-pressing sintering have been subjected to helium plasma at 1050 K with ion energy of 100 eV for one hour in a linear plasma generator STEP. The W–V alloys consist of three typical phase regions, i.e. the W-enriched region, the W–V solid solute region and the V-enriched region. Slight surface erosion on the W–V solid solute region and severe surface erosion on the V-enriched region are observed on the exposed surface. Sputtering during the He plasma loading contributed to the surface erosion in the W–V solid solute region and the V-enriched region. Slight sputtering on W–V solid solute region is expected given that the lighter alloying element increases the sputtering yield of the W-based material. Moreover, fuzz nanostructure formed on the surface of the W–V alloys under the applied irradiation conditions. The W–V solid solute region exhibits severe fuzz growth in comparison with the W-enriched region when exposed to He plasma, especially in the low flux area. The intense attraction interaction between He and substitutional V atoms aggravates the fuzz growth on the W–V solid solute region. Furthermore, the aggravation effect of V on fuzz nanostructure evolution is mitigated in the high flux area due to the enhanced preferential V sputtering.

日本語訳

ホットプレス焼結により作製した5および10 wt.% Vを含むタングステン–バナジウム(W–V)合金を、線形プラズマ発生装置STEPにおいて、イオンエネルギー100 eV、温度1050 Kのヘリウムプラズマに1時間曝露した。W–V合金は、W濃化領域、W–V固溶体領域、V濃化領域の3つの典型的な相領域から構成される。曝露表面では、W–V固溶体領域にわずかな表面侵食、V濃化領域に激しい表面侵食が観察された。Heプラズマ負荷中のスパッタリングが、W–V固溶体領域およびV濃化領域の表面侵食に寄与した。より軽い合金元素がW基材料のスパッタリング収率を増加させることを考慮すると、W–V固溶体領域でのわずかなスパッタリングが予想される。さらに、適用した照射条件下でW–V合金の表面にファズナノ構造が形成された。W–V固溶体領域は、Heプラズマに曝露された際、特に低フラックス領域において、W濃化領域と比較して激しいファズ成長を示す。Heと置換型V原子との間の強い引力相互作用が、W–V固溶体領域でのファズ成長を悪化させる。さらに、高フラックス領域では、優先的なVスパッタリングの増強により、ファズナノ構造形成に対するVの悪化効果は緩和される。

wiki

TungstenHeliumSTEPLinear plasmaHelium plasma
この論文にはまだAI要約がありません。

関連論文

Surface modification of W–V alloy exposed to high heat flux helium neutral beams

2018Nuclear Fusion

Surface modification of W–Ta–V–Cr multi-component alloy after low-energy He plasma irradiation

2024Nuclear Fusion

Surface modification of ZrC dispersion-strengthened W under low energy He plasma irradiation

2024Nuclear Fusion

Simulation of fuzz formation on tungsten surface and its impact on sputtering and hydrogen retention by MD-MC hybrid method

2026Nuclear Fusion

The evolutionary process of W-V mixed dumbbell in tungsten crystals: A study about W-V alloy as a plasma-facing material in fusion devices

2024Fusion Engineering and Design

Effects of fibre-form nanostructures on particle emissions from a tungsten surface in plasmas

2012Nuclear Fusion

The dependence of tungsten fuzz layer thickness and porosity on tungsten deposition rate and helium ion fluence

2024Nuclear Fusion

Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material

2022Nuclear Fusion

Initial growth of tungsten fuzz induced by bubble-driven surface stress layer under helium irradiation

2023Plasma Physics and Controlled Fusion

Helium concentration measurement in tungsten fuzz-like nanostructures by means of thermal desorption spectroscopy

2016Nuclear Fusion