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Carbon erosion/deposition on the divertor of W7-X during the operational period OP 1.2b

M. Mayer, M. Balden, S. Brezinsek, V.V. Burwitz, C. Cupak, C.P. Dhard, S. Elgeti, M. Guitart Corominas, P. Hiret, M. Kandler2022年被引用 2Nuclear FusionIF 3出版社

Carbon net erosion and deposition at the test divertor unit (TDU) of Wendelstein 7-X (W7-X) were measured for the discharge period OP 1.2b in the year 2018 using 18 specially prepared target elements in all 10 TDUs. These had lengths between 30 and 60 cm and were coated with marker layers for erosion/deposition investigations of 5–10 μm carbon on top of about 300 nm molybdenum. The marker layer thicknesses were measured by elastic backscattering spectrometry (EBS) before and after plasma exposure using 2.5 MeV protons; the surface morphology was investigated using scanning electron microscopy (SEM) and focused ion beam cross-sectioning (FIB), the surface roughness was determined using a two-dimensional optical profiler. Plasma-exposed surfaces were considerably smoother than unexposed surfaces with decreased mean roughness and a shift of the inclination angle distribution towards lower values. The erosion on the 10 TDUs was unequal within a factor of about two. During the discharge period in total 20.4 ± 5.7 g carbon was eroded from the 10 TDUs. Adjacent to the strike line some deposition of carbon was observed. Compared to the discharge period OP 1.2a in the year 2017, the net carbon erosion rate dropped by a factor of 5–6 due to regular boronizations, which reduced the oxygen (and subsequently also the carbon) content in the plasma by 1–2 orders of magnitude. The significance of erosion/deposition processes for long-pulse discharges is discussed.

日本語訳

Wendelstein 7-X(W7-X)のテストダイバータユニット(TDU)における炭素の正味の侵食と堆積を、2018年の放電期間OP 1.2bにおいて、10基すべてのTDUに設置した特別に準備された18個のターゲット要素を用いて測定した。これらの要素は長さ30~60 cmであり、約300 nmのモリブデンの上に5~10 μmの炭素からなるマーカー層がコーティングされ、侵食・堆積の調査に供された。マーカー層の厚さは、2.5 MeVの陽子を用いた弾性後方散乱分光法(EBS)により、プラズマ曝露の前後で測定された。表面形態は走査型電子顕微鏡(SEM)および集束イオンビーム断面加工(FIB)を用いて調査され、表面粗さは二次元光学プロファイラを用いて測定された。プラズマ曝露面は非曝露面と比較して著しく平滑化されており、平均粗さの減少と傾斜角分布の低角度側へのシフトが観察された。10基のTDUにおける侵食量は約2倍の範囲でばらつきがあった。放電期間全体を通じて、10基のTDUから合計20.4 ± 5.7 gの炭素が侵食された。ストライクライン近傍では炭素の堆積が一部観察された。2017年の放電期間OP 1.2aと比較して、正味の炭素侵食速度は5~6倍低下した。これは、定期的なホウ素化によりプラズマ中の酸素(およびそれに伴う炭素)含有量が1~2桁低減したためである。長パルス放電に対する侵食・堆積プロセスの重要性について考察する。

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