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

Understanding and suppressing the near scrape-off layer heat flux feature in inboard-limited plasmas in TCV

F. Nespoli, B. Labit, I. Furno, J. Horacek, C.K. Tsui, J.A. Boedo, R. Maurizio, H. Reimerdes, C. Theiler, P. Ricci2017年被引用 16Nuclear FusionIF 3出版社

In inboard-limited plasmas, the scrape-off layer (SOL) shows two regions: the near SOL, extending a few mm from the last closed flux surface (LCFS), characterized by a steep gradient of the parallel heat flux radial profile, and a far SOL, typically some cm wide, with flatter heat flux profiles. The physics of the near SOL is investigated in TCV with two series of experiments featuring deuterium and helium plasmas, in which the plasma current, density and elongation have been varied. The parallel heat flux profiles are measured on the limiter by means of infrared thermography. For the first time, the near SOL is reported to disappear for low plasma current or at high density, for values of the SOL collisionality corresponding to a conduction-limited regime. The power in the near SOL is shown to decrease with the normalized Spitzer resistivity ν as . The floating potential profiles, measured at the limiter using flush-mounted Langmuir probes (LP), show the presence of non-ambipolar currents, and their relation to the presence of a velocity shear layer is discussed. The shearing rate is shown to strictly correlate with the power in the near SOL , consistently with a recent theoretical model. Measurements of the near SOL on the Low Field Side (LFS) are performed using a reciprocating Langmuir probe (RP). The near SOL is reported to vanish simultaneously at the LFS and at the limiter. The near and far SOL widths are compared with the predictions from existing theoretical models, to which empirical corrections with resistivity and elongation are proposed.

日本語訳

閉じ込められたプラズマにおいて、スクレイプオフ層(SOL)は2つの領域を示す:最終閉鎖磁気面(LCFS)から数mm広がる近接SOL領域で、平行熱流束の径方向プロファイルが急峻な勾配を示すこと、および、典型的には数cmの幅を持つ遠方SOL領域で、熱流束プロファイルがより平坦であること。TCVにおける近接SOLの物理を、重水素およびヘリウムプラズマを用いた2系列の実験で調査した。これらの実験では、プラズマ電流、密度、および伸長度を変化させた。平行熱流束プロファイルは、赤外線サーモグラフィを用いてリミッター上で測定した。伝導制限領域に対応するSOL衝突度の値において、低プラズマ電流または高密度の場合に近接SOLが消失することを初めて報告した。近接SOL内のパワーは、規格化スピッツァー抵抗率ν*の増加とともに減少することを示した。リミッター上で埋め込み型ラングミュアプローブ(LP)を用いて測定した浮遊電位プロファイルは、非双極性電流の存在を示し、それらの速度シア層の存在との関連について議論した。シア率は、最近の理論モデルと一致して、近接SOL内のパワーと厳密に相関することを示した。低磁場側(LFS)における近接SOLの測定は、往復動ラングミュアプローブ(RP)を用いて実施した。近接SOLは、LFSおよびリミッターの両方で同時に消失することが報告された。近接および遠方SOLの幅を既存の理論モデルの予測と比較し、抵抗率および伸長度に対する経験的補正を提案した。

wiki

Scrape-off layerTCV
この論文にはまだAI要約がありません。

関連論文

Heat flux decay length during RF power operation in the Tore Supra tokamak

2014Nuclear Fusion

Diffusive–convective transition for scrape-off layer transport and the heat-flux width

2012Plasma Physics and Controlled Fusion

A Monte Carlo model for velocity space effects in low recycling scrape-off layer plasmas

1996Nuclear Fusion

An extensive analysis of SOL properties in high-δ plasmas in ASDEX Upgrade

2024Nuclear Fusion

Turbulent transport in the scrape-off layer of Wendelstein 7-X

2021Nuclear Fusion

Scrape-off layer properties of ITER-like limiter start-up plasmas in JET

2013Nuclear Fusion

Impact of the non-axisymmetric SOL current driven by a biased electrode on the diverted J-TEXT plasma

2022Plasma Physics and Controlled Fusion

Relating the near SOL transport with plasma properties of the confined edge region in ASDEX Upgrade

2019Plasma Physics and Controlled Fusion

Study of near scrape-off layer (SOL) temperature and density gradient lengths with Thomson scattering

2015Plasma Physics and Controlled Fusion

Role of electric currents for the SOL and divertor target heat fluxes in ASDEX Upgrade

2020Plasma Physics and Controlled Fusion