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W7-AS: One step of the Wendelstein stellarator line.

Authors :
Wagner, F.
B&äumel, S.
Baldzuhn, J.
Basse, N.
Brakel, R.
Burhenn, R.
Dinklage, A.
Dorst, D.
Ehmler, H.
Endler, M.
Erckmann, V.
Feng, Y.
Gadelmeier, F.
Geiger, J.
Giannone, L.
Grigull, P.
Hartfuss, H.-J.
Hartmann, D.
Hildebrandt, D.
Hirsch, M.
Source :
Physics of Plasmas; Jul2005, Vol. 12 Issue 7, p072509, 22p
Publication Year :
2005

Abstract

This paper is a summary of some of the major results from the Wendelstein 7-AS stellarator (W7-AS). W7-AS [G. Grieger et al., Phys. Fluids B 4, 2081 (1992)] has demonstrated the feasibility of modular coils and has pioneered the island divertor and the modeling of its three-dimensional characteristics with the EMC3/EIRENE code [Y. Feng, F. Sardei et al., Plasma Phys. Controlled Fusion 44, 611 (2002)]. It has extended the operational range to high density (4×10<superscript>20</superscript> m<superscript>-3</superscript> at 2.5 T) and high 〈β〉 (3.4% at 0.9 T); it has demonstrated successfully the application of electron cyclotron resonance heating (ECRH) beyond cutoff via electron Bernstein wave heating, and it has utilized the toroidal variation of the magnetic field strength for ion cyclotron resonance frequency beach-wave heating. In preparation of W7-X [J. Nührenberg et al., Trans. Fusion Technol. 27, 71 (1995)], aspects of the optimization concept of the magnetic design have been successfully tested. W7-AS has accessed the H-mode, the first time in a “non-tokamak” and has extended H-mode operation toward high density by the discovery of the high-density H-mode (HDH), characterized by H-mode energy and L-mode-level impurity confinement. In the HDH-mode quasisteady state operation is possible close to operational limits without noticeable degradation in the plasma properties. High-β phases up to t<subscript>pulse</subscript>/τ<subscript>E</subscript>=65 have been achieved, which can already be taken as an indication of the intrinsic stellarator capability of steady-state operation. Confinement issues will be discussed with emphasis on the similarities to tokamak confinement (general transport properties, H-mode transition physics) but also with respect to distinct differences (no confinement degradation toward operational boundaries, positive density scaling, lack of profile resilience, no distinct isotope effect, H-mode operational window). W7-AS turned out to be an important step in the development of the Wendelstein stellarator line towards an independent fusion power plant concept. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
1070664X
Volume :
12
Issue :
7
Database :
Complementary Index
Journal :
Physics of Plasmas
Publication Type :
Academic Journal
Accession number :
18133350
Full Text :
https://doi.org/10.1063/1.1927100