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Lithium wall conditioning techniques in ADITYA-U tokamak for impurity and fuel control

K.A. Jadeja, J. Ghosh, Nandini Yadava, K.M. Patel, Kiran Patel, R.L. Tanna, R. Manchanda, M.B. Chowdhuri, J.V. Raval, U.C. Nagora2022年被引用 7Nuclear FusionIF 3出版社

In fusion devices, various techniques are employed for coating the plasma facing components (PFCs) including the vessel wall with low-Z material like lithium, boron, and silicon in order to enhance the plasma parameters and control. In ADITYA-Upgrade tokamak, different techniques of lithium wall conditioning are developed and implemented to obtain uniform and sustainable coating of Li on PFCs and the vessel wall. In this paper, two techniques used to generate Li from the source are reported. In one of the technique, a heated (fixed temperature of ∼120 °C) Li-rod is placed inside the hydrogen glow discharge cleaning (H-GDC) plasma and the sputtered Li by hydrogen (H) ions and atoms coats the wall and periphery. In the second technique, the Li is vapourized using a high-temperature Li-evaporator and released into the H-GDC plasma for uniform coating of Li on the PFCs and vessel. Significantly enhanced plasma parameters are obtained after Li coating by both techniques, with the evaporated Li performed better than the Li rod case. With the Li coating obtained with evaporated Li at 600 °C (550 mg Li) with H-GDC, the Li wall conditioning has been observed to be sustaining for in a larger number of plasma discharges in comparison to non-H-GDC assisted Li deposition. As the melting temperature of lithium hydride (LiH) is much higher (688.7 °C) than that of lithium (180.5 °C), this enhance the longer Li-coating lifetime relatively due to the formation of Li–H molecules on the vessel wall and PFCs. In ADITYA-U the carbon impurity and hydrogen recycling, due to relatively high surface area of graphite PFCs as well as their proximity to the plasma, limits the plasma performance and effective controls. Hence, H-GDC, H-GDC with Li-rod sputtering or Li evaporation, helium-GDC, argon–hydrogen mixtures-GDC in particular sequence are carried out to obtain better plasma discharges. The Li coating techniques and their effect on tokamak plasma discharges of ADITYA-U are discussed in this paper.

日本語訳

核融合装置では、プラズマパラメータと制御を向上させるために、リチウム、ホウ素、ケイ素などの低Z材料を容器壁を含むプラズマ対向機器(PFC)に被覆するための様々な技術が採用されている。ADITYA-Upgradeトカマクでは、PFCおよび容器壁上に均一かつ持続可能なLi被覆を得るために、異なるリチウム壁調整技術が開発され、実装されている。本論文では、線源からLiを生成するために用いられる2つの技術について報告する。1つの技術では、加熱された(固定温度約120 °C)Liロッドを水素グロー放電洗浄(H-GDC)プラズマ内に配置し、水素(H)イオンおよび原子によってスパッタリングされたLiが壁および周辺部を被覆する。2つ目の技術では、高温Li蒸着装置を用いてLiを蒸発させ、H-GDCプラズマ中に放出してPFCおよび容器上に均一なLi被覆を得る。両技術によるLi被覆後、プラズマパラメータは大幅に向上し、蒸着Liの方がLiロッドの場合よりも優れた性能を示した。600 °C(550 mg Li)で蒸着したLiとH-GDCを用いて得られたLi被覆では、非H-GDC支援のLi堆積と比較して、より多くのプラズマ放電にわたってLi壁調整が持続することが観察された。水素化リチウム(LiH)の融点(688.7 °C)はリチウムの融点(180.5 °C)よりもはるかに高いため、容器壁およびPFC上でのLi–H分子の形成により、Li被覆の寿命が比較的長く延長される。ADITYA-Uでは、グラファイトPFCの比較的大きな表面積およびプラズマへの近接性に起因する炭素不純物と水素リサイクリングが、プラズマ性能と効果的な制御を制限している。したがって、より良好なプラズマ放電を得るために、H-GDC、LiロッドスパッタリングまたはLi蒸発を伴うH-GDC、ヘリウムGDC、アルゴン-水素混合ガスGDCが特定の順序で実施される。本論文では、ADITYA-Uのトカマクプラズマ放電に対するLi被覆技術とその効果について議論する。

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ImpurityLithiumADITYAADITYA-UWall conditioning
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