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          Institute: MPI für Plasmaphysik     Collection: Articles, Books, Inbooks     Display Documents



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ID: 111827.0, MPI für Plasmaphysik / Articles, Books, Inbooks
Experiments close to the beta-limit in W7-AS
Authors:Weller, A.; Geiger, J.; Werner, A.; Zarnstorff, M. C.; Nührenberg, C.; Sallander, E.; Baldzuhn, J.; Brakel, R.; Burhenn, R.; Dinklage, A.; Fredrickson, E.; Gadelmeier, F.; Giannone, L.; Grigull, P.; Hartmann, D.; Jaenicke, R.; Klose, S.; Knauer, J. P.; Könies, A.; Kolesnichenko, Ya. I.; Laqua, H. P.; Lutsenko, V. V.; McCormick, K.; Monticello, D.; Osakabe, M.; Pasch, E.; Reiman, A.; Rust, N.; Spong, D. A.; Wagner, F.; Yakovenko, Yu. V.; W7-AS Team; NBI-Group
Language:English
Research Context:30th European Physical Society Conference on Controlled Fusion and Plasma Physics, St. Petersburg, 2003-07-07 to 2003-07-01
Date of Publication (YYYY-MM-DD):2003
Title of Journal:Plasma Physics and Controlled Fusion
Journal Abbrev.:Plasma Phys. Control. Fusion
Volume:45
Issue / Number:A12
Start Page:A285
End Page:A308
Title of Issue:Invited papers from the 30th European Physical Society Conference on Controlled Fusion and Plasma Physics
Copyright:Copyright © Institute of Physics and IOP Publishing Limited 2003
Review Status:Peer-review
Audience:Experts Only
Abstract / Description:A major objective of the experimental program in the last phase of the W7-AS stellarator was to explore and demonstrate the high-β performance of advanced stellarators. MHD-quiescent discharges at low impurity radiation levels with volume averaged β-values of up to ‹β›= 3.4% have been achieved. A very important prerequisite was the attainment of the high density H-Mode (HDH) regime. This was made possible by the installation of extensive graphite plasma facing components designed for island divertor operation. The co-directed neutral beam injection provided increased absorbed heating power of up to 3.2 MW in high-β plasmas with B ≤ 1.25 T. The anticipated improved features concerning equilibrium and stability at high plasma β could be verified experimentally by the comparison of x-ray data with free boundary equilibrium calculations. The maximum β found in configurations with a rotational transform around ι= 0.5 is determined by the available heating power. No evidence of a stability limit has been found in the accessible configuration space, and the discharges are remarkably quiescent at maximum β, most likely due the increase of the magnetic well depth. An increase in low m/n MHD activity is typically observed during the transition towards high β. The beneficial stability properties of net-current-free configurations could be demonstrated by comparison with configurations where a significant inductive current drive was involved. Current driven instabilities such as tearing modes and soft disruptions can prevent access to β-values as high as in the currentless case. The experimental results indicate that optimized stellarators such as W7-X can be considered as a viable option for an attractive stellarator fusion reactor.
External Publication Status:published
Document Type:Article
Communicated by:N. N.
Affiliations:MPI für Plasmaphysik/E5
External Affiliations:Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA; Institute for Nuclear Research, 03680 Kyiv, Ukraine; National Institute for Fusion Science, Oroshi-cho 322-6. Toki, 509-5292, Japan; Oak Ridge National Laboratory, Oak Ridge, TN 37831-8071, USA
Identifiers:DOI:10.1088/0741-3335/45/12A/019
URL:http://stacks.iop.org/0741-3335/45/A285
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