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RF heating in stellarators

T Watari1998年Plasma Physics and Controlled FusionIF 2.2出版社

Nuclear fusion research has made considerable progress using tokamaks, and detailed design for a reactor-sized tokamak, ITER, is now under way. On the other hand, the stellarator has been considered to be alternative to the tokamak and there has been considerable progress recently. Plasma heating has been the most important theme of investigation in stellarator research as well as in tokamak research. This paper refers to a few key aspects of stellarator plasma heating in the existing experiments CHS and W7-AS. Efforts to understand the physical meaning of the experimental results in terms of neoclassical theory are also introduced. Throughout this review, the particular importance of particle orbits will be emphasized and the performance of plasma heating in the coming next-generation devices such as LHD and W7-X will be estimated according to the model employed.

日本語訳

核融合研究はトカマクを用いてかなりの進展を遂げており、炉規模のトカマクであるITERの詳細設計が現在進行中である。一方、ステラレータはトカマクに代わる方式と考えられており、近年かなりの進展が見られている。プラズマ加熱は、トカマク研究と同様にステラレータ研究においても最も重要な研究テーマである。本論文では、既存の実験装置CHSおよびW7-ASにおけるステラレータプラズマ加熱のいくつかの重要な側面について述べる。また、新古典理論の観点から実験結果の物理的意味を理解する取り組みについても紹介する。本レビューを通じて、粒子軌道の重要性が特に強調され、採用されたモデルに従って、LHDやW7-Xなどの次世代装置におけるプラズマ加熱の性能が評価される。

装置

iter中精度(概要文一致)lhd中精度(概要文一致)wendelstein-7x中精度(概要文一致)

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Stellarator
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