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In-vessel surface layer evolution during plasma–wall interaction in the Globus-M spherical tokamak

V.K. Gusev, V.Kh. Alimov, I.I. Arkhipov, B.Ya. Ber, A.E. Gorodetsky, N.A. Khromov, A.A. Kurdumov, V.M. Lebedev, N.V. Litunovsky, I.V. Mazul2009年被引用 5Nuclear FusionIF 3出版社

The composition, morphology and structure of the mixed layers deposited onto the surface (deposits) after a preliminary carboboronization procedure (B/C : H layers deposition) and subsequent plasma–wall interaction in the different areas of the Globus-M spherical tokamak have been analysed. Globus-M is almost completely covered by recrystallized graphite protection tiles (currently about 90% of its inner vessel area facing to plasma). The deposit properties were examined by different diagnostic techniques (electron probe microanalysis, scanning electron microscope, x-ray diffraction, nuclear resonance reactions, thermal desorption spectroscopy, infrared Raman scattering and secondary ion mass spectroscopy) after sample exposure to plasma during 3000–10000 tokamak pulses. It was found that deposits existed even in high flux regions (separatrix strike points). The initial composition of the protective layers formed during boronization is dramatically modified during long-term plasma–wall interaction and resulted in significant intermixing of its components with materials of the vessel interior. The properties of the layers deposited onto the surfaces intensively interacting with plasma, as well as the composition of the layers deposited in the 'shadowed' zones are discussed. Deuterium retention in Globus-M was estimated relying upon the data on deuterium concentrations in the deposits that were measured by different methods. It is revealed that deuterium was absorbed only in the deposits and its concentration vanished in the bulk of the tiles. Conditions of deuterium desorption are analysed and the merits of recrystallized graphite are discussed.

日本語訳

球形托卡马克Glob-Mの異なる領域における、予備カーボボロナイジング処理(B/C:H層堆積)後の混合層の堆積物と、その後のプラズマ・壁相互作用について分析を行った。Glob-Mは、ほぼ全面的に再結晶化グラファイト製保護タイルで覆われている(現在、プラズマ対向面の約90%を占める)。試料を3000~10000回のトカマク放電に曝露した後、電子プローブ微小分析、走査型電子顕微鏡、X線回折、核共鳴反応、熱脱離分光法、赤外分光法、ラマン散乱、二次イオン質量分析などの様々な診断手法を用いて、堆積物の特性を評価した。その結果、高フラックス領域(セパラトリックス打撃点)においても堆積物の存在が確認された。ボロナイジング処理中に形成された保護層の初期組成は、長時間のプラズマ・壁相互作用によって劇的に変化し、容器内部の材料との顕著な混合が生じた。プラズマと強く相互作用する表面に堆積した層の特性と、いわゆる「影の領域」に堆積した層の組成について考察する。Glob-Mにおける重水素の滞留は、様々な方法で測定された堆積物中の重水素濃度のデータに基づいて評価された。その結果、重水素は堆積物中にのみ吸収され、タイルのバルク中には存在しないことが明らかになった。重水素の脱離条件を分析し、再結晶化グラファイトの利点について考察する。

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Spherical tokamakIn-vessel componentsPlasma-wall interactionGlobus-M
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