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Edge properties with the liquid lithium limiter in FTU—experiment and transport modelling

V Pericoli-Ridolfini, M L Apicella, G Mazzitelli, O Tudisco, R Zagórski, the FTU team2007年Plasma Physics and Controlled FusionIF 2.2出版社

Liquid lithium as a plasma-facing material was tested for the first time on a high field medium size tokamak, FTU. A liquid Li reservoir supplies a mesh of capillaries that is movable from shot to shot in the scrape-off layer (SOL) plasma to act as a secondary limiter. An almost complete lithization of the vacuum vessel walls is obtained in about three discharges. Plasmas cleaner than boronization and titanization, with lower radiation losses and smaller impurity content are produced. The SOL electron temperature increases, ΔTe ∼ 10 eV, while density (ne) is less affected. The 2D multifluid code TECXY explains this only if a strong reduction of plasma recycling on the walls and main limiter occurs, consistent with the high Li hydrogen pumping capability. This property also permits a much tighter control of the plasma density. With the Li limiter inserted inside the vessel poloidal asymmetries develop in the SOL that TECXY explains with a local increase of radiation, caused by enhanced evaporation/sputtering of Li. New regimes can be produced in such conditions with a clear increase in |∇ne/ne| and of the peaking factor ne0/ <ne ≫ 2 at the Greenwald density limit , without any direct central particle fuelling.

日本語訳

液体リチウムをプラズマ対向材料として、高磁場中規模トカマクFTUにおいて初めて試験した。液体Liリザーバーは、ショットごとに移動可能な毛細管メッシュを供給し、スクレイプオフ層(SOL)プラズマ中で二次リミターとして機能する。約3回の放電で、真空容器壁のほぼ完全なリチウム化が達成された。ボロン化やチタン化と比較して、より清浄なプラズマが得られ、放射損失と不純物含有量が低減した。SOL電子温度は増加し(ΔTe ∼ 10 eV)、一方で密度(ne)への影響は小さかった。2次元多流体コードTECXYによる解析は、壁および主リミターでのプラズマリサイクリングが大幅に低減した場合にのみ実験結果を説明でき、これはLiの高い水素ポンピング能力と一致する。この特性により、プラズマ密度のより精密な制御が可能となる。Liリミターを容器内に挿入すると、SOL内でポロイダル非対称性が発達し、TECXYはこれをLiの蒸発・スパッタリング増強による局所的な放射増加で説明する。これらの条件下では、グリーンワルド密度限界において|∇ne/ne|およびピーキング係数ne0/⟨ne⟩が明確に増加する新たな運転領域が実現可能であり、中心部への直接的な粒子供給を必要としない。

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LithiumLimiterLiquid lithiumFTU
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