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Investigation and plasma cleaning of first mirrors coated with relevant ITER contaminants: beryllium and tungsten

L. Moser, R.P. Doerner, M.J. Baldwin, C.P. Lungu, C. Porosnicu, M. Newman, A. Widdowson, E. Alves, G. Pintsuk, J. Likonen2017年被引用 17Nuclear FusionIF 3出版社

In order to extend the investigation of the plasma cleaning of ITER first mirrors, a set of molybdenum mirrors was coated in a laboratory with ITER-relevant contaminants, namely beryllium and tungsten. Different coating techniques as well as several contaminant compositions were used to ensure a large variety of films to clean, completing a previous study conducted on mirrors exposed in the JET ITER-like wall (tokamak deposits) [1]. Due to the toxicity of beryllium, the samples were treated in a vacuum chamber specially built for this purpose. The cleaning was performed using capacitively coupled RF plasma and evaluated by performing reflectivity measurements, scanning electron microscopy, x-ray photoelectron spectroscopy and ion beam analysis. The removal of all types of contaminants was achieved by using different plasma compositions (argon, helium and mixtures of the two) with various ion energies (from 200–600 eV) and in some cases the mirror's reflectivity was restored towards initial values. Pure helium discharges were capable of removing mixed beryllium/tungsten layers and oxidized molybdenum. In addition, no significant increase in the diffuse reflectivity of the mirrors was observed for the helium cleaning, though this was the case for some samples cleaned with argon. Helium is therefore appropriate for cleaning all mirrors in ITER leading to a possible cleaning regime where the entire vessel is filled with He and all mirrors are cleaned simultaneously without damaging their surfaces.

日本語訳

ITER第一鏡のプラズマ洗浄の調査を拡張するため、一連のモリブデン鏡にITER関連の汚染物質、すなわちベリリウムとタングステンを実験室でコーティングした。洗浄すべき多様な膜を確保するために、異なるコーティング技術と複数の汚染物質組成を用いた。これは、JETのITER類似壁(トカマク堆積物)に曝露された鏡を用いて実施された先行研究を補完するものである[1]。ベリリウムの毒性のため、試料はこの目的のために特別に建設された真空チャンバー内で処理された。洗浄は容量結合型RFプラズマを用いて実施され、反射率測定、走査型電子顕微鏡、X線光電子分光法、イオンビーム分析によって評価された。すべての種類の汚染物質の除去は、異なるプラズマ組成(アルゴン、ヘリウム、およびそれらの混合物)と様々なイオンエネルギー(200〜600 eV)を用いることで達成され、いくつかの場合では鏡の反射率は初期値に向かって回復した。純ヘリウム放電は、混合ベリリウム/タングステン層および酸化モリブデンの除去が可能であった。さらに、ヘリウム洗浄では鏡の拡散反射率の有意な増加は観察されなかったが、アルゴンで洗浄したいくつかの試料ではこれが観察された場合があった。したがって、ヘリウムはITERのすべての鏡の洗浄に適しており、容器全体をHeで満たし、表面を損傷することなくすべての鏡を同時に洗浄するという可能な洗浄方式につながる。

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