分流器
温德尔斯坦7-X
恒星仪
等离子体
护盾
迷惑
材料科学
沉积(地质)
环面
隔热板
相(物质)
石墨
核工程
电磁屏蔽
复合材料
托卡马克
物理
核物理学
工程类
热力学
古生物学
生物
量子力学
沉积物
作者
C. P. Dhard,M. Balden,T. Braeuer,S. Brezinsek,J.W. Coenen,Andrzej Dudek,G. Ehrke,D. Hathiramani,S. Klose,R. König,M. Laux,Ch. Linsmeier,A. Manhard,S. Masuzaki,M. Mayer,G. Motojima,D. Naujoks,R. Neu,O. Neubauer,M. Rack
出处
期刊:Physica Scripta
[IOP Publishing]
日期:2017-09-13
卷期号:2017 (T170): 014010-014010
被引量:11
标识
DOI:10.1088/1402-4896/aa86fb
摘要
Abstract In the Wendelstein 7-X stellarator with its twisted magnetic geometry the investigation of plasma wall interaction processes in 3D plasma configurations is an important research subject. For the upcoming operation phase i.e. OP1.2, three different types of material probes have been installed within the plasma vessel for the erosion/deposition investigations in selected areas with largely different expected heat load levels, namely, ≤10 MW m −2 at the test divertor units (TDU), ≤500 kW m −2 at the baffles, heat shields and toroidal closures and ≤100 kW m −2 at the stainless steel wall panels. These include 18 exchangeable target elements at TDU, about 30 000 screw heads at graphite tiles and 44 wafer probes on wall panels, coated with marker layers. The layer thicknesses, surface morphologies and the impurity contents were pre-characterized by different techniques and subjected to various qualification tests. The positions of these probes were fixed based on the strike line locations on the divertor predicted by field line diffusion and EMC3/EIRENE modeling calculations for the OP1.2 plasma configurations and availability of locations on panels in direct view of the plasma. After the first half of the operation phase i.e. OP1.2a the probes will be removed to determine the erosion/deposition pattern by post-mortem analysis and replaced by a new set for the second half of the operation phase, OP1.2b.
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