Tungsten erosion in the baffle and outboard regions of the ITER-like ASDEX Upgrade divertor

被引:19
作者
Maier, H [1 ]
机构
[1] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany
关键词
D O I
10.1016/j.jnucmat.2004.09.002
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Similar to the design of the next-step device ITER, ASDEX Upgrade is equipped with vertical divertor targets with adjacent baffles extending towards the main chamber. In ITER, it is intended to employ tungsten as a plasma-facing material in this baffle area. Tungsten-coated graphite tiles were installed in the divertor baffle and the outboard side regions of ASDEX Upgrade for a full experimental campaign. The erosion behavior of tungsten was investigated by scanning electron microscopy and by measuring the thickness of the tungsten coatings before and after exposure. The coatings had an initial thickness of approximately 450 nm. Two distinct erosion mechanisms were observed: in the outer baffle region a reduction of the coatings' thickness up to 100 nm was determined after about 6300 s of plasma discharge. On the roof baffle and on the inner baffle modules, no clear reduction of the film thickness was found. In the tracks of arcs, however, the tungsten coatings were completely removed. This represents an erosion of 5-10% of the tungsten-coated surface area in this region. (C) 2004 Elsevier B.V. All rights reserved.
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收藏
页码:515 / 519
页数:5
相关论文
共 23 条
[1]  
[Anonymous], 1995, Handbook of Modern Ion Beam Material Analysis
[2]   ITER status, design and material objectives [J].
Aymar, R .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :1-9
[3]   Simulated annealing analysis of Rutherford backscattering data [J].
Barradas, NP ;
Jeynes, C ;
Webb, RP .
APPLIED PHYSICS LETTERS, 1997, 71 (02) :291-293
[4]   Plasma facing and high heat flux materials - needs for ITER and beyond [J].
Bolt, H ;
Barabash, V ;
Federici, G ;
Linke, J ;
Loarte, A ;
Roth, J ;
Sato, K .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :43-52
[5]   MACROPARTICLE CONTAMINATION IN CATHODIC ARC COATINGS - GENERATION, TRANSPORT AND CONTROL [J].
BOXMAN, RL ;
GOLDSMITH, S .
SURFACE & COATINGS TECHNOLOGY, 1992, 52 (01) :39-50
[6]   Plasma-material interactions in current tokamaks and their implications for next step fusion reactors [J].
Federici, G ;
Skinner, CH ;
Brooks, JN ;
Coad, JP ;
Grisolia, C ;
Haasz, AA ;
Hassanein, A ;
Philipps, V ;
Pitcher, CS ;
Roth, J ;
Wampler, WR ;
Whyte, DG .
NUCLEAR FUSION, 2001, 41 (12R) :1967-2137
[7]  
JANESCHITZ G, 2002, J NUCL MATER, V290, P293
[8]   Elemental thin film depth profiles by ion beam analysis using simulated annealing - a new tool [J].
Jeynes, C ;
Barradas, NP ;
Marriott, PK ;
Boudreault, G ;
Jenkin, M ;
Wendler, E ;
Webb, RP .
JOURNAL OF PHYSICS D-APPLIED PHYSICS, 2003, 36 (07) :R97-R126
[9]   Conclusions about the use of tungsten in the divertor of ASDEX Upgrade [J].
Krieger, K ;
Maier, H ;
Neu, R .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :207-216
[10]   Erosion and migration of tungsten employed at the main chamber first wall of ASDEX upgrade [J].
Krieger, K ;
Geier, A ;
Gong, X ;
Maier, H ;
Neu, R ;
Rohde, V .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :327-332