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

Intrinsic current driven by electromagnetic electron drift wave turbulence in the tokamak pedestal region

Wen He, Lu Wang, Ge Zhuang2019年Plasma Physics and Controlled FusionIF 2.2出版社

The local intrinsic parallel current density driven by electron drift wave (DW) turbulence including electromagnetic (EM) effects is analytically studied. The scalings of the ratios of intrinsic current density driven by residual turbulent flux and by a turbulent source to the bootstrap (BS) current density with electron density and temperature are predicted to be and respectively. Based on the typical parameters in the DIII-D pedestal region, the local intrinsic current density driven by both the residual turbulent flux and the turbulent source is negligible. However, despite the negligible turbulent source driven current, the residual turbulent flux driven local intrinsic current density by EM DW turbulence can reach about 66% of the BS current density for International Thermonuclear Experimental Reactor (ITER) pedestal parameters due to much lower collisionality in ITER than in DIII-D. Moreover, the contributions from adiabatic ES parts, non-adiabatic ES parts, and non-adiabatic EM parts of the plasma response to EM fluctuations are analyzed. It is found that there is a strong cancellation between the non-adiabatic ES response and the non-adiabatic EM response for the ITER pedestal case, and thus the kinetic stress contributed by the adiabatic ES response of parallel electron pressure dominates the intrinsic current drive. This is different from the ES electron DW case. Therefore, the EM effects on turbulence driven intrinsic current density should be carefully considered in the future reactor with a high ratio of electron pressure to the magnetic pressure and steep pressure profile.

日本語訳

電子ドリフト波(DW)乱流によって駆動される、電磁(EM)効果を含む局所的な固有平行電流密度を解析的に研究した。残留乱流フラックスおよび乱流源によって駆動される固有電流密度とブートストラップ(BS)電流密度との比のスケーリングは、電子密度および電子温度に対してそれぞれ および と予測される。DIII-Dペデスタル領域における典型的なパラメータに基づくと、残留乱流フラックスと乱流源の両方によって駆動される局所的な固有電流密度は無視できる程度である。しかしながら、乱流源によって駆動される電流が無視できるにもかかわらず、EM DWによって駆動される残留乱流フラックス由来の局所的な固有電流密度は、ITERの方がDIII-Dよりも衝突頻度がはるかに低いため、ITERペデスタルパラメータにおいてBS電流密度の約66%に達し得る。さらに、EM変動に対するプラズマ応答のうち、断熱的ES成分、非断熱的ES成分、および非断熱的EM成分の寄与を解析した。ITERペデスタルの場合、非断熱的ES応答と非断熱的EM応答の間には強い打ち消し合いが存在し、その結果、平行電子圧力の断熱的ES応答によって寄与される運動論的応力が固有電流駆動を支配することが見出された。これはES電子ドリフト波の場合とは異なる。したがって、電子圧力と磁気圧の比が高く、圧力勾配が急峻な将来の炉においては、乱流駆動固有電流密度に対するEM効果を慎重に考慮すべきである。

装置

diii-d中精度(概要文一致)iter中精度(概要文一致)

wiki

Current drivePedestalDrift wavesDrift wave turbulence
この論文にはまだAI要約がありません。

関連論文

Intrinsic current driven by electromagnetic electron temperature gradient turbulence in tokamak plasmas

2018Nuclear Fusion

Parametric dependence of turbulent particle transport in high density electron heated FTU plasmas

2007Plasma Physics and Controlled Fusion

Contributions of the cross phase to the plasma transport

2017Plasma Physics and Controlled Fusion

Study on the turbulence transition in the pedestal of high-density H-mode plasmas in EAST

2025Nuclear Fusion

Core density turbulence in the HSX Stellarator

2015Nuclear Fusion

Electrostatic turbulence in EAST plasmas with internal transport barrier

2023Nuclear Fusion

DIII-D shaping demonstrates correlation of intrinsic momentum with energy

2019Nuclear Fusion

Turbulent transport of heat and particles in a high ion temperature discharge of the Large Helical Device

2015Nuclear Fusion

Understanding of the density profile shape, electron heat transport and internal transport barriers observed in ASDEX Upgrade

2005Nuclear Fusion

Global gyrokinetic simulations of intrinsic rotation in ASDEX Upgrade Ohmic L-mode plasmas

2018Nuclear Fusion