Overview of wall probes for erosion and deposition studies in the TEXTOR tokamak

被引：24
|
作者：
Rubel, M. [1 ]
Brezinsek, S. [2 ,3 ]
Coenen, J. W. [2 ,3 ]
Huber, A. [2 ,3 ]
Kirschner, A. [2 ,3 ]
Kreter, A. [2 ,3 ]
Petersson, P. [1 ]
Philipps, V. [2 ,3 ]
Pospieszczyk, A. [2 ,3 ]
Schweer, B. [2 ,3 ]
Sergienko, G. [2 ,3 ]
Tanabe, T. [4 ]
Ueda, Y. [5 ]
Wienhold, P. [2 ,3 ]
机构：
[1] Royal Inst Technol, Dept Fus Plasma Phys, S-10044 Stockholm, Sweden
[2] Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany
[3] TEC, D-52425 Julich, Germany
[4] Kyushu Univ, Interdisciplinary Grad Sch Engn Sci, Fukuoka, Fukuoka, Japan
[5] Osaka Univ, Grad Sch Engn, Osaka 5650871, Japan
来源：
MATTER AND RADIATION AT EXTREMES | 2017年 / 2卷 / 03期
关键词：
Erosion-deposition; Material migration; Deuterium retention; Carbon; Tungsten; TEXTOR; SCRAPE-OFF LAYER; PLASMA-FACING COMPONENTS; CONTROLLED FUSION DEVICES; TUNGSTEN TEST-LIMITERS; TWIN-TEST-LIMITER; HIGH HEAT LOAD; ITER-LIKE WALL; FUEL RETENTION; IMPURITY RELEASE; MATERIAL PERFORMANCE;
D O I：
10.1016/j.mre.2017.03.002
中图分类号：
O4 [物理学];
学科分类号：
0702 ;
摘要：
An overview of diagnostic tools - test limiters and collector probes - used over the years for material migration studies in the TEXTOR tokamak is presented. Probe transfer systems are shown and their technical capabilities are described. This is accompanied by a brief presentation of selected results and conclusions from the research on material erosion - deposition processes including tests of candidate materials (e.g. W, Mo, carbon-based composites) for plasma-facing components in controlled fusion devices. The use of tracer techniques and methods for analysis of materials retrieved from the tokamak are summarized. The impact of research on the reactor wall technology is addressed. (C) 2017 Science and Technology Information Center, China Academy of Engineering Physics. Publishing services by Elsevier B.V.
引用
收藏
页码：87 / 104
页数：18
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