Tungsten as plasma-facing material in ASDEX upgrade

被引：66

作者：

Neu, R ^{[1
]}

Dux, R ^{[1
]}

Geier, A ^{[1
]}

Gruber, O ^{[1
]}

Kallenbach, A ^{[1
]}

Krieger, K ^{[1
]}

Maier, H ^{[1
]}

Pugno, R ^{[1
]}

Rohde, V ^{[1
]}

Schweizer, S ^{[1
]}

机构：

[1] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2003年 / 65卷 / 03期

关键词：

tungsten components; high-Z material; first wall materials; erosion; impurity transport; CENTRAL COLUMN; TOKAMAK; CONFINEMENT; COATINGS; GRAPHITE; BEHAVIOR; EROSION; REGION; TILES;

D O I：

10.1016/S0920-3796(02)00381-2

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Since 1993, a tungsten programme is run at ASDEX Upgrade, leading to the installation of a complete W-divertor in 1995 followed by 1 year of operation. From 1998 onwards, an increasing area of tungsten-coated tiles has been installed at the central column of ASDEX Upgrade, reaching an area of 7.1 m(2) in 2001/2002 representing about 85% of the total area of the central column. The programme comprises not only the operation with large area W-coatings but also the qualification and testing of the coated tiles, W-erosion and -migration investigations, development of spectroscopic diagnostics and interpretation of the observed W-behaviour by impurity transport calculations. During the campaigns with the W-divertor as well as with W-coated central column, almost no negative influence on the plasma performance was found. The W-erosion is dominated by light intrinsic impurities and typical tungsten concentrations in the main plasma range from below 10(-6) Up to a few times 10(-5), which would be sufficiently low for a burning plasma. (C) 2003 Elsevier Science B.V. All rights reserved.

引用

页码：367 / 374

页数：8

共 35 条

[1] Spectroscopic investigations of tungsten in the EUV region and the determination of its concentration in tokamaks [J].

Asmussen, K ;

Fournier, KB ;

Laming, JM ;

Neu, R ;

Seely, JF ;

Dux, R ;

Engelhardt, W ;

Fuchs, JC .

NUCLEAR FUSION, 1998, 38 (07) :967-986

[2]

ASMUSSEN K, 1997, EUR C ABSTR, P1393

[3] The physics of the International Thermonuclear Experimental Reactor FEAT [J].

Campbell, DJ .

PHYSICS OF PLASMAS, 2001, 8 (05) :2041-2049

[4] Neoclassical impurity transport in the core of an ignited tokamak plasma [J].

Dux, R ;

Peeters, AG .

NUCLEAR FUSION, 2000, 40 (10) :1721-1729

[5] Accumulation of impurities in advanced scenarios [J].

Dux, R ;

Giroud, C ;

Neu, R ;

Peeters, AG ;

Stober, J ;

Zastrow, KD .

JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :1150-1155

[6] In-vessel tritium retention and removal in ITER [J].

Federici, G ;

Anderl, RA ;

Andrew, P ;

Brooks, JN ;

Causey, RA ;

Coad, JP ;

Cowgill, D ;

Doerner, RP ;

Haasz, AA ;

Janeschitz, G ;

Jacob, W ;

Longhurst, GR ;

Nygren, R ;

Peacock, A ;

Pick, MA ;

Philipps, V ;

Roth, J ;

Skinner, CH ;

Wampler, WR .

JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :14-29

[7] High-heat-flux loading of tungsten coatings on graphite deposited by plasma spray and physical vapor deposition [J].

GarciaRosales, C ;

Deschka, S ;

Hohenauer, W ;

Duwe, R ;

Gauthier, E ;

Linke, J ;

Lochter, M ;

Mallener, WKWM ;

Plochl, L ;

Rodhammer, P ;

Salito, A .

FUSION TECHNOLOGY, 1997, 32 (02) :263-276

[8]

Konig R.W.T., 2001, J. Nucl. Mater, V290-293, P882

[9] Plasma-wall interaction at the ASDEX Upgrade tungsten heat shield [J].

Krieger, K ;

Maier, H ;

Neu, R ;

Rohde, V ;

Tabasso, A .

FUSION ENGINEERING AND DESIGN, 2001, 56-57 :189-193

[10]

Krieger K., 1999, J NUCL MATER, V207, P266

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