Plasma surface interaction with tungsten in ASDEX Upgrade

被引:19
作者
Dux, R [1 ]
Herrmann, A [1 ]
Kallenbach, A [1 ]
Neu, R [1 ]
Neuhauser, J [1 ]
Maier, H [1 ]
Pugno, R [1 ]
Pütterich, T [1 ]
Rohde, V [1 ]
机构
[1] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany
关键词
first wall materials; tungsten; erosion; ASDEX Upgrade;
D O I
10.1016/j.jnucmat.2004.10.105
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
ASDEX Upgrade pursues the progressive increase of W coated plasma facing components. At present, the central column, the upper passive stabiliser loop, the complete upper divertor, the baffles at the lower divertor, as well as six tiles of one guard limiter at the low field side are W coated, representing about 65% of the total surface area. W erosion at these guard limiter tiles exceeds the erosion found at other main chamber components by more than one order of magnitude, and spectroscopically determined erosion yields indicate a strong contribution from fast particles. Upper single null discharges do not show an obviously increased W content compared to discharges run in the lower C based divertor. (c) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:852 / 856
页数:5
相关论文
共 15 条
[1]   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
[2]   Influence of the heating profile on impurity transport in ASDEX Upgrade [J].
Dux, R ;
Neu, R ;
Peeters, AG ;
Pereverzev, G ;
Mück, A ;
Ryter, F ;
Stober, J .
PLASMA PHYSICS AND CONTROLLED FUSION, 2003, 45 (09) :1815-1825
[3]  
ECKSTEIN W, 1993, 982 IPP MPI PLASM
[4]  
ECKSTEIN W, 2002, 9132 IPP MPI PLASM
[5]   Heat flux decay length in the midplane of ASDEX Upgrade [J].
Herrmann, A ;
Carlson, A ;
Fuchs, JC ;
Gruber, O ;
Laux, M ;
Neuhauser, J ;
Pugno, R ;
Sips, A ;
Treutterer, W ;
Schneider, W .
JOURNAL OF NUCLEAR MATERIALS, 2001, 290 :619-622
[6]   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
[7]   Tungsten erosion in the baffle and outboard regions of the ITER-like ASDEX Upgrade divertor [J].
Maier, H .
JOURNAL OF NUCLEAR MATERIALS, 2004, 335 (03) :515-519
[8]   Development of tungsten coated first wall and high heat flux components for application in ASDEX Upgrade [J].
Maier, H ;
Luthin, J ;
Balden, M ;
Lindig, S ;
Linke, J ;
Rohde, V ;
Bolt, H .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) :116-120
[9]   Properties of tungsten coatings deposited onto fine grain graphite by different methods [J].
Maier, H ;
Luthin, J ;
Balden, M ;
Linke, J ;
Koch, F ;
Bolt, H .
SURFACE & COATINGS TECHNOLOGY, 2001, 142 :733-737
[10]   New results from the tungsten programme at ASDEX Upgrade [J].
Neu, R ;
Dux, R ;
Geier, A ;
Greuner, H ;
Krieger, K ;
Maier, H ;
Pugno, R ;
Rohde, V ;
Yoon, SW .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :116-126