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Design, and initial experiment results of a novel LH launcher on Alcator C-Mod

S. Shiraiwa, O. Meneghini, R.R. Parker, G. Wallace, J. Wilson, I. Faust, C. Lau, R. Mumgaard, S. Scott, S. Wukitch2011年被引用 32Nuclear FusionIF 3出版社

The design, construction and initial results of a new lower hybrid current drive (LHCD) launcher on Alcator C-Mod (Hutchinson et al 1994 Phys. Plasmas1 1511) are presented. The new LHCD launcher (LH2) is based on a novel splitter concept which evenly distributes the microwave power in four ways in the poloidal direction. This design allows for simplification of the feeding structure while keeping the flexibility to vary the peak launched toroidal index of refraction, Ntoroidal, from −3.8 to 3.8. An integrated model predicts good plasma coupling over a wide range of edge densities, while poloidal variations of the edge density are found to affect the evenness of power splitting in the poloidal direction. The measured transmission loss is about 30% lower than the previous launcher, and a clean Ntoroidal spectrum has been confirmed. Power handling capability exceeding an empirical weak conditioning limit and reliable operation up to 1.1 MW net LHCD power have been achieved. A survey of antenna–plasma coupling shows the existence of a millimetric vacuum gap in front of the launcher. Fully non-inductive, reversed shear plasma operation has been demonstrated and sustained for multiple current diffusion times. The current drive efficiency, ηLH ≡ neR0Ip/PLH, of these plasmas is (0.2–0.25) × 1020 m−2A W−1, which is in agreement with the expected efficiency on the International Thermonuclear Experimental Reactor (ITER).

日本語訳

要約:Alcator C-Mod(Hutchinsonら1994 Phys. Plasmas1 1511)における新しい低域混成波電流駆動(LHCD)ランチャーの設計、製作、初期結果を提示する。新しいLHCDランチャー(LH2)は、ポロイダル方向にマイクロ波電力を4方向に均等に分配する新規なスプリッター概念に基づく。この設計により、給電構造の簡素化が可能となり、同時にピークのトロイダル屈折率N_トロイダルを−3.8から3.8の範囲で変化させる柔軟性を維持する。統合モデルは、広範囲のエッジ密度にわたって良好なプラズマ結合を予測する一方、エッジ密度のポロイダル変動がポロイダル方向の電力分配の均一性に影響を与えることが見出された。測定された伝送損失は、以前のランチャーより約30%低く、クリーンなN_トロイダルスペクトルが確認された。電力処理能力は、経験的な弱い限界値を超え、1.1 MWの正味LHCD電力で信頼性の高い運転が達成された。アンテナ・プラズマ結合の調査により、ランチャー前面にミリメートル規模の真空ギャップの存在が示された。完全非誘導、逆転磁気シアープラズマ運転が実証され、複数の電流拡散時間にわたって維持された。電流駆動効率η_LH ≡ n_e R I_p / P_LHは(0.2–0.25)×10^20 m^−2 A W^−1であり、国際熱核融合実験炉(ITER)で予想される効率と一致する。

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