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Divertor operation in stellarators: results from W7-AS and implications for future devices

Authors :
M. Hirsch
R. Jaenicke
Suguru Masuzaki
A. Werner
D. Hildebrandt
P. Grigull
F. Sardei
Dirk Naujoks
U. Wenzel
H. Renner
F. Gadelmeier
Friedrich E. Wagner
Thomas Klinger
E. Pasch
W As Team
J. P. Knauer
R. Burhenn
H. Ehmler
J. Baldzuhn
N. Ramasubramanian
H. Niedermeyer
D. Hartmann
R. Brakel
J. Kisslinger
K. McCormick
Y. Feng
L. Giannone
R. König
S. Bäumel
Source :
Fusion Engineering and Design. :49-58
Publication Year :
2003
Publisher :
Elsevier BV, 2003.

Abstract

The research on divertors for stellarators is at the beginning. Extensive studies are being prepared on large helical device (LHD) and W7-X. W7-AS is now being operated with an open island divertor (ID) which serves as a test bed for the W7-X diverter. The divertor enables access to a new NBI-heated, high-density operating regime with improved confinement properties. This regime-the high-density H-mode (HDH)-displays no evident mode activity, is extant above a threshold density and characterized by flat density profiles. high-energy- and low-impurity-confinement times and edge-localized radiation. Impurity accumulation, normally associated with ELM-free H-modes, is avoided. Quasi-steady-state discharges with n e up to 4 x 10 20 m -3 , edge radiation levels up to 90% and plasma partial detachment at the divertor targets can be simultaneously realized. The accessibility to other improved confinement modes in W7-AS (conventional H-mode anti OC-mode) is not restricted by the divertor. The results provide a promising basis for future experiments, in particular on W7-X, and recommend the ID as a serious candidate for solving the plasma exhaust problem in stellarators.

Details

ISSN :
09203796
Database :
OpenAIRE
Journal :
Fusion Engineering and Design
Accession number :
edsair.doi...........966b1158832edfdc3a8385897ceb0711
Full Text :
https://doi.org/10.1016/s0920-3796(03)00121-2