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A helical magnetic limiter for boundary layer control in large tokamaks

W. Feneberg, G.H. Wolf1981年被引用 80Nuclear FusionIF 3出版社

In a tokamak configuration, superposition of the magnetic field of resonant helical windings which surround the toroidal plasma current outside the first wall destroys the magnetic surfaces in the boundary layer (ergodization). A transport model is analysed, where convective flow of the plasma from the boundary layer to the first wall permits elevated particle densities in the boundary layer and leads to very high particle and energy transport. The convective flow is driven by the pressure gradient along the field lines which intersect the toroidal wall at an oblique small angle . The required thickness Δ of the boundary layer is around 1015 n−1·cm−2. As a result, the plasma temperature there can be reduced towards the threshold of critical plasma-wall-interaction processes, the plasma core can be shielded against impurities from the wall and, at the same time, a very short life-time of all particles in the boundary layer can be achieved (use of pumpholes and/or scrape-off-limiters for removing ash). Thus, this model also improves the concepts of edge radiation cooling. An estimate is given of the parameters of INTOR using only a weak helical perturbation field which conserves the magnetic surfaces in the plasma core: one can reach wall temperatures Tw between 20 and 30 eV in the presence of wall densities nw approaching 1014cm−3.

日本語訳

トカマク配位において、第一壁の外側でトロイダルプラズマ電流を取り囲む共鳴ヘリカル巻線の磁場を重畳すると、境界層における磁気面が破壊される(エルゴダイゼーション)。境界層から第一壁へのプラズマの対流流が、境界層内の粒子密度の上昇を可能にし、非常に高い粒子・エネルギー輸送をもたらす輸送モデルを解析する。対流流は、トロイダル壁と斜めの小さな角度で交差する磁力線に沿った圧力勾配によって駆動される。境界層の必要厚さΔは、およそ10^15 n^−1·cm^−2である。その結果、そこでのプラズマ温度は、臨界プラズマ-壁相互作用過程の閾値に向けて低下させることができ、プラズマコアは壁からの不純物に対して遮蔽され得る。同時に、境界層内のすべての粒子の非常に短い寿命を達成できる(灰分除去のためのポンプホールおよび/またはスクレイプオフリミッターの使用)。したがって、このモデルは端部放射冷却の概念も改善する。プラズマコア内の磁気面を保存する弱いヘリカル摂動場のみを用いたINTORのパラメータの推定値を示す:壁密度n_wが10^14 cm^−3に近づく状況下で、壁温度T_wを20から30 eVの間に到達させることができる。

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