Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade

被引：146

作者：

Dux, R. ^{[1
]}

Bobkov, V. ^{[1
]}

Herrmann, A. ^{[1
]}

Janzer, A. ^{[1
]}

Kallenbach, A. ^{[1
]}

Neu, R. ^{[1
]}

Mayer, M. ^{[1
]}

Mueller, H. W. ^{[1
]}

Pugno, R. ^{[1
]}

Puetterich, T. ^{[1
]}

Rohde, V. ^{[1
]}

Sips, A. C. C. ^{[1
]}

机构：

[1] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 390-91卷

关键词：

ALCATOR C-MOD; DIVERTOR; EROSION; TRANSPORT; TOKAMAK;

D O I：

10.1016/j.jnucmat.2009.01.225

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

ASDEX Upgrade has successfully started the second experimental campaign with a full tungsten coverage of the plasma facing components and without using a boronisation for machine conditioning. The tungsten erosion at all relevant positions in the main chamber and the divertor were investigated. The outer divertor is by far the strongest source region, especially in discharges with high divertor temperature in-between ELMs. In the main chamber, the central column is usually the first limiting structure and produces then larger W erosion fluxes than the outboard limiters. Nevertheless, the tungsten influx from the outboard limiters has a much stronger effect on the tungsten content in the confined plasma. An increase of the available power from the fly-wheel generator allowed for improved H-mode operation at 1 MA, and H factors in the range of 1.2 could be achieved at acceptable W concentrations of about 2 x 10(-5). (C) 2009 Elsevier B.V. All rights reserved.

引用

页码：858 / 863

页数：6

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