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Development of ITER non-activation phase operation scenarios

S.H. Kim, F.M. Poli, F. Koechl, E. Militello-Asp, A.R. Polevoi, R. Budny, T.A. Casper, A. Loarte, T.C. Luce, Y.-S. Na2017年被引用 10Nuclear FusionIF 3出版社

Non-activation phase operations in ITER in hydrogen (H) and helium (He) will be important for commissioning of tokamak systems, such as diagnostics, heating and current drive (HCD) systems, coils and plasma control systems, and for validation of techniques necessary for establishing operations in DT. The assessment of feasible HCD schemes at various toroidal fields (2.65–5.3 T) has revealed that the previously applied assumptions need to be refined for the ITER non-activation phase H/He operations. A study of the ranges of plasma density and profile shape using the JINTRAC suite of codes has indicated that the hydrogen pellet fuelling into He plasmas should be utilized taking the optimization of IC power absorption, neutral beam shine-through density limit and H-mode access into account. The EPED1 estimation of the edge pedestal parameters has been extended to various H operation conditions, and the combined EPED1 and SOLPS estimation has provided guidance for modelling the edge pedestal in H/He operations. The availability of ITER HCD schemes, ranges of achievable plasma density and profile shape, and estimation of the edge pedestal parameters for H/He plasmas have been integrated into various time-dependent tokamak discharge simulations. In this work, various H/He scenarios at a wide range of plasma current (7.5–15 MA) and field (2.65–5.3 T) have been developed for the ITER non-activation phase operation, and the sensitivity of the developed scenarios to the used assumptions has been investigated to provide guidance for further development.

日本語訳

ITERにおける水素(H)およびヘリウム(He)を用いた非活性化段階の運転は、トカマクシステム、例えば診断、加熱・電流駆動(HCD)システム、コイル、プラズマ制御システムの試運転、およびDT運転の確立に必要な技術の検証にとって重要である。様々なトロイダル磁場(2.65–5.3 T)における実現可能なHCD方式の評価により、ITERの非活性化段階におけるH/He運転に対して、これまで適用されてきた仮定を改良する必要があることが明らかになった。JINTRACコード群を用いたプラズマ密度と密度分布形状の範囲に関する研究により、水素ペレット入射をHeプラズマへ適用する際には、IC電力吸収、中性粒子ビームのシンクアウト密度限界、Hモード到達条件を考慮した最適化が必要であることが示された。EPED1モデルによる周辺ペデスタルパラメータの推定は様々なH運転条件に拡張され、EPED1とSOLPSを組み合わせた評価は、H/He運転における周辺ペデスタルのモデリングに指針を提供した。ITERの非活性化段階の運転に対して、広範囲のプラズマ電流(7.5–15 MA)およびトロイダル磁場(2.65–5.3 T)にわたる様々なH/Heシナリオが構築され、これらのシナリオの各種仮定に対する感度が調査され、今後の発展に向けた指針が示された。

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