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Analysis of tokamak configurations using the toroidal multipole method

F. Alladio, F. Crisanti, M. Marinucci, P. Micozzi, A. Tanga1991年被引用 10Nuclear FusionIF 3出版社

An exact prediction of the plasma contour is important for the design of new tokamaks and for the definition of the operational scenarios of existing machines. Certain features of the plasma boundary, such as elongation and triangularity, and a detailed description of the X-point region are relevant for the plasma-limiter interaction. The toroidal multipolar moment method has been used, with fixed boundary conditions, to produce the required plasma shape. The resulting vacuum flux function has been reproduced, using the poloidal coil currents that minimize the magnetic energy as best parameters for the fitting. Examples are given for the single and double X-point configurations in JET and ITER.

日本語訳

プラズマの形状を正確に予測することは、新しいトカマクの設計や、既存の装置における運転シナリオの定義にとって重要である。プラズマ境界の特定の特性、例えば、三角形度や伸長度、そしてX点領域の詳細な記述は、プラズマ・リミター相互作用に関連する。トロイダル多極子モーメント法は、固定された境界条件のもとで、要求されるプラズマ形状を生成するために用いられてきた。得られた真空磁束関数は、磁気エネルギーを最小化するポロイダルコイル電流を最適なフィッティングパラメータとして用いて再現された。JETおよびITERにおける単一X点および二重X点配位の例が示されている。

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iter中精度(概要文一致)jet中精度(概要文一致)
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