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Characteristics of ergodic divertor plasmas in the Tore Supra tokamak

C. De Michelis, A. Grosman, X. Garbet, P. Ghendrih, M. Goniche, W. Hess, C. Laviron, T. Loarer, M. Mattioli, P. Monier-Garbet1995年被引用 31Nuclear FusionIF 3出版社

The characteristics of ergodic divertor (ED) deuterium plasmas in the Tore Supra tokamak are discussed. The divertor volume is a relatively well limited region between the ED modules and ρ = τ/a equivalent to 0.8. The core (ρ ⩽ 0.8) plasma confinement is not degraded by the presence of the ED (by comparison with similar limiter, non-ED plasmas): the electron density and temperature profiles are not modified. The ED configuration compares well with a classical X point divertor: intrinsic impurities are screened out, the power load is deflected to dedicated surfaces, and density control through particle pumping is possible. Up to 5.5 MW of ion cyclotron resonance power and 3 MW of lower hybrid power have been successfully used, power exhaust being mainly by radiation (80%)

日本語訳

トカマク型装置Tore Supraにおけるエルゴディック・ダイバータ(ED)重水素プラズマの特性について論じる。ダイバータ領域は、EDモジュールとρ = τ/a(等価値0.8)の間の比較的限定された領域である。コア(ρ ≤ 0.8)プラズマ閉じ込めは、EDの存在によって劣化しない(類似のリミター非EDプラズマとの比較による):電子密度および電子温度分布は変化しない。ED配位は古典的なX点ダイバータと良好な比較を示す:固有不純物は遮蔽され、熱負荷は専用表面へ偏向され、粒子排気による密度制御が可能である。最大5.5 MWのイオンサイクロトロン共鳴加熱電力と3 MWの低混成波加熱電力が正常に投入され、排熱は主に放射(80%)によるものである。

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DivertorTore SupraDivertor plasmaErgodic divertor
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