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 ECRH on the stability of the radiation induced m = 2 mode and on the current quench of a major disruption

F. Salzedas, A.A.M. Oomens, F.C. Schüller, the RTP team2002年被引用 13Nuclear FusionIF 3出版社

The results of a series of experiments done in RTP which had the purpose to avoid or ameliorate radiative density-limit disruptions, will be reported. Avoidance of disruptions was achieved by stabilizing the m = 2 radiation induced tearing mode (RTM) with electron cyclotron resonance heating (ECRH). Both continuous and modulated power deposition was studied. It was found that stabilization with modulated ECRH in phase with the O-point was less efficient than continuous ECRH, contrary to theoretical expectations. Detailed scans of the EC power deposition and of the power intensity were in agreement with the assumption that radiative heat loss is the driving mechanism of this m = 2 mode. Amelioration of disruptions was achieved, in a pilot experiment, by applying ECRH at the end of the energy quench. In this way, the current decay that follows a major density-limit disruption could be reversed.

日本語訳

RTPで実施された、放射状密度限界ディスラプションを回避または緩和することを目的とした一連の実験の結果を報告する。ディスラプションの回避は、電子サイクロトロン共鳴加熱(ECRH)によりm = 2放射誘起ティアリングモード(RTM)を安定化することで達成された。連続および変調の両方のパワー堆積が研究された。O点と位相を合わせた変調ECRHによる安定化は、理論的予想に反して、連続ECRHよりも効率が低いことが判明した。ECパワー堆積およびパワー強度の詳細なスキャンは、放射熱損失がこのm = 2モードの駆動メカニズムであるという仮定と一致した。パイロット実験では、エネルギー急減の終了時にECRHを印加することによりディスラプションの緩和が達成された。この方法により、主要な密度限界ディスラプションに続く電流減衰を反転させることができた。

wiki

Plasma disruptionElectron cyclotron heating
この論文にはまだAI要約がありません。

関連論文

Disruption avoidance by means of electron cyclotron waves

2011Plasma Physics and Controlled Fusion

The m=2, n=1 mode suppression by ECRH on the T-10 tokamak

1997Nuclear Fusion

Disruption control on FTU and ASDEX upgrade with ECRH

2009Nuclear Fusion

Electron cyclotron resonance heating on the TCA tokamak

1993Nuclear Fusion

Microwave diagnostics damage by parametric decay instabilities during electron cyclotron resonance heating in ASDEX Upgrade

2021Plasma Physics and Controlled Fusion

Observation of TAE mode driven by off-axis ECRH induced barely trapped energetic electrons in EAST tokamak

2021Nuclear Fusion

Overview of the recent experimental research on the J-TEXT tokamak

2024Nuclear Fusion

The ballistic jump of the total heat flux after ECRH switching on in the T-10 tokamak

2004Plasma Physics and Controlled Fusion

Avoidance of disruptions at high βN in ASDEX Upgrade with off-axis ECRH

2011Nuclear Fusion

ECRH power deposition studies in ASDEX Upgrade

2002Plasma Physics and Controlled Fusion