Survey of dust formed in the TEXTOR tokamak: structure and fuel retention

被引：29

作者：

Ivanova, D. ^{[1
]}

Rubel, M. ^{[1
]}

Philipps, V. ^{[2
]}

Freisinger, M. ^{[2
]}

Huang, Z. ^{[1
]}

Penkalla, H. ^{[2
]}

Schweer, B. ^{[2
]}

Sergienko, G. ^{[2
]}

Sundelin, P. ^{[1
]}

Wessel, E. ^{[2
]}

机构：

[1] Assoc EURATOM VR, Alfven Lab, Royal Inst Technol, S-10044 Stockholm, Sweden

[2] Assoc EURATOM FZJ, Forschungszentrum Julich, Inst Energy Res, D-52425 Julich, Germany

来源：

PHYSICA SCRIPTA | 2009年 / T138卷

关键词：

CONTROLLED FUSION DEVICES; CO-DEPOSITED LAYERS; PLASMA-FACING COMPONENTS; HIGH HEAT-FLUX; CARBON; PARTICLES; EROSION; ITER; CONSEQUENCES; EMISSION;

D O I：

10.1088/0031-8949/2009/T138/014025

中图分类号：

O4 [物理学];

学科分类号：

0702 ;

摘要：

A detailed survey of erosion and deposition on plasma-facing components was performed in the TEXTOR tokamak. Co-deposits and dust particles were collected from graphite limiters and from several locations on the Inconel liner. The total amount of dust (loose material), originating mainly from carbon-rich co-deposits detached from the limiters and the liner, was around 2 g, with sizes from 0.1 mu m to 1 mm. The morphology and fuel retention was determined using microscopy methods, ion beam analysis and thermal desorption spectrometry. The study revealed differences in structure and fuel content between deposits from the toroidal and main poloidal limiters. There were also splashes, up to 1 mm in diameter, of molten metal (mainly nickel) on the toroidal limiters. Issues of the dust conversion factor (erosion-to-dust) are addressed and a comparison with results of previous dust surveys at TEXTOR is also briefly presented.

引用

页数：6

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