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

Edge loss of high-harmonic fast-wave heating power in NSTX: a cylindrical model

R.J. Perkins, J.C. Hosea, N. Bertelli, G. Taylor, J.R. Wilson2017年被引用 4Nuclear FusionIF 3出版社

Efficient high-harmonic fast-wave (HHFW) heating in the National Spherical Torus Experiment Upgrade (NSTX-U) would facilitate experiments in turbulence, transport, fast-ion studies, and more. However, previous HHFW operation in NSTX exhibited a large loss of fast-wave power to the divertor along the scrape-off layer field lines for edge densities above the fast-wave cutoff. It was postulated that the wave amplitude is enhanced in the scrape-off layer due to cavity-like modes, and that these enhanced fields drive sheath losses through RF rectification. As part of ongoing work to confirm this hypothesis, we have developed a cylindrical cold-plasma model to identify and understand scenarios where a substantial fraction of wave power is confined to the plasma periphery. We previously identified a peculiar class of modes, named annulus resonances, that conduct approximately half of their wave power in the periphery and can also account for a significant fraction of the total wave power. Here, we study the influence of annulus resonances on wave field reconstructions and find instances where annulus-resonant modes dominate the spectrum and trap over half of the total wave power at the edge. The work is part of an ongoing effort to determine the mechanism underlying these scrape-off layer losses in NSTX, identify optimal conditions for operation in NSTX-U, and predict whether similar losses occur for the ion-cyclotron minority heating scheme for both current experiments and future devices such as ITER.

日本語訳

高調波高速波(HHFW)加熱が国立球状トーラス実験装置アップグレード(NSTX-U)において効率的に実現されれば、乱流、輸送、高速イオン研究などの実験が促進されるであろう。しかしながら、これまでのNSTXにおけるHHFW運転では、端部密度が高調波遮断密度を超える場合に、スクレイプオフ層の磁力線に沿ってダイバータへの高速波パワーの大きな損失が観測された。空洞様モードによりスクレイプオフ層内で波動振幅が増大し、その増大した電場がRF整流を通じてシース損失を駆動するという仮説が提唱された。この仮説を検証する進行中の研究の一環として、我々は円筒状冷プラズマモデルを構築し、波動パワーの実質的な割合がプラズマ周辺部に閉じ込められるシナリオを特定し理解することを試みた。我々は以前に、アニュラス共鳴と名付けた特異なモード群を特定した。これらのモードは、その波動パワーの約半分を周辺部で伝導し、全波動パワーの有意な割合を占めることもできる。本稿では、アニュラス共鳴が波動場再構成に及ぼす影響を調査し、アニュラス共鳴モードがスペクトルを支配し、全波動パワーの半分以上を端部に閉じ込める事例を見出した。この研究は、NSTXにおけるスクレイプオフ層損失の根本メカニズムを解明し、NSTX-Uにおける最適運転条件を特定し、さらに電流駆動実験およびITERのような将来の装置の両方におけるイオンサイクロトロン周波数帯域のマイノリティ加熱スキームについて同様の損失が発生するかどうかを予測するための継続的な取り組みの一部である。

装置

nstx-u高精度(タイトル一致)iter低精度(概要文一致)

wiki

Fusion Advanced Studies TorusNSTXWave heating
この論文にはまだAI要約がありません。

関連論文

Full wave simulations of fast wave efficiency and power losses in the scrape-off layer of tokamak plasmas in mid/high harmonic and minority heating regimes

2016Nuclear Fusion

Spectral effects on fast wave core heating and current drive

2009Nuclear Fusion

Full wave simulations of fast wave heating losses in the scrape-off layer of NSTX and NSTX-U

2014Nuclear Fusion

Simulations towards the achievement of non-inductive current ramp-up and sustainment in the National Spherical Torus Experiment Upgrade

2015Nuclear Fusion

Modeling of high harmonic fast wave scenarios for NSTX Upgrade

2019Nuclear Fusion

Ion cyclotron resonance heating fast and slow wave excitation and power deposition in edge plasmas with application to ITER

2021Plasma Physics and Controlled Fusion

Coupling to the fast wave at lower hybrid frequencies

1980Nuclear Fusion

Parametric decay instability during high harmonic fast wave heating experiments on the TST-2 spherical tokamak

2009Nuclear Fusion

Wave penetration and power deposition of helicon current drive for magnetic fusion plasma with sharp edge gradient

2025Plasma Physics and Controlled Fusion

Calculation of coupling to the electron Bernstein wave with a phased waveguide array

2005Plasma Physics and Controlled Fusion