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In-vessel coils for magnetic error field correction in JT-60SA

JT-60SAにおける誤差磁場補正のための容器内コイル

松永 剛; 武智 学; 櫻井 真治; 鈴木 康浩*; 井手 俊介; 浦野 創

Matsunaga, Go; Takechi, Manabu; Sakurai, Shinji; Suzuki, Yasuhiro*; Ide, Shunsuke; Urano, Hajime

JT-60SA is designed and under construction as fully superconducting tokamak under a combined project of the ITER satellite tokamak program of EU-JA (Broader Approach Activities) and the Japanese national program. One of the main purposes of JT-60SA is the steady-state high-beta operation above the ideal no-wall beta limit. To achieve this, we have designed in-vessel coils, thus error filed correction coils (EFCCs) for a correction of magnetic error fields that affect plasma initiation and induce magnetic island locking. We will report the design of the EFCC in JT-60SA from an engineering and a physics points of view.

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パーセンタイル:18.76

分野:Nuclear Science & Technology

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