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Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices

S V Mirnov, E A Azizov, V A Evtikhin, V B Lazarev, I E Lyublinski, A V Vertkov, D Yu Prokhorov2006年Plasma Physics and Controlled FusionIF 2.2出版社

The paper is an overview of recent results of Li limiter testing in T-11M tokamak. The lithium limiter is based on the capillary-pore system (CPS) concept. The Li erosion process and deuterium (D2) and helium (He) sorption by Li first wall were investigated. The ability of capillary forces to confine the liquid Li in the CPS limiter during disruption was demonstrated. The idea of combined lithium limiter with thin (0.6 mm) CPS coating as a solution of the heat removal problem was realized. As a result the quasi steady-state tokamak regime with duration up to 0.3 s and clean (Zeff = 1) deuterium plasma has been achieved. The temporal evolution of the lithium surface temperature during discharge was measured by a IR radiometer and then was recalculated to the surface power load. For the estimation of the Li limiter erosion the Li neutral and ions spectral line emission were observed. The increase in lithium erosion as a result of limiter heating was discovered. The radial distribution of plasma column radiation measurements showed up to 90% of the total radiation losses in a relatively thin (5 cm) boundary layer and only 10% in a plasma centre during discharges with high Li influx. Oscillations of Li emission and saw-tooth-like oscillations of the limiter surface temperature have been detected in discharge regimes with highest Li limiter temperature (>600 °C). A version of Li CPS first wall of DEMO reactor and Li CPS limiter experiment in the International Thermonuclear Energy Reactor are suggested.

日本語訳

本論文は、T-11Mトカマクにおけるリチウムリミッター試験の最近の結果の概要である。リチウムリミッターは、キャピラリーポアシステム(CPS)の概念に基づいている。Li第一壁によるリチウムの侵食過程と重水素(D2)およびヘリウム(He)の吸着過程を調査した。ディスラプション中にCPSリミッター内の液体Liを閉じ込めるキャピラリー力の能力が実証された。熱除去問題の解決策として、薄い(0.6 mm)CPSコーティングを施した複合リチウムリミッターのアイデアが実現された。その結果、持続時間が最大0.3秒の準定常トカマク運転と、クリーンな(Zeff = 1)重水素プラズマが達成された。放電中のリチウム表面温度の時間的変化は、IR放射温度計によって測定され、その後、表面熱負荷に再計算された。Liリミッターの侵食評価のため、Li中性原子およびイオンのスペクトル線発光が観測された。リミッター加熱の結果としてリチウム侵食が増加することが発見された。高Li流入を伴う放電中、プラズマ柱の放射測定の動径分布は、総放射損失の最大90%が比較的薄い(5 cm)境界層で生じ、プラズマ中心部ではわずか10%のみであることを示した。最も高いLiリミッター温度(>600°C)を伴う放電モードにおいて、Li発光の振動とリミッター表面温度の鋸歯状振動が検出された。DEMO炉用のLi CPS第一壁のバージョンと、国際熱核融合実験炉におけるLi CPSリミッター実験が提案されている。

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