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  Experiments close to the beta-limit in W7-AS

Weller, A., Geiger, J., Werner, A., Zarnstorff, M. C., Nührenberg, C., Sallander, E., et al. (2003). Experiments close to the beta-limit in W7-AS. Invited papers from the 30th European Physical Society Conference on Controlled Fusion and Plasma Physics, A285-A308. doi:10.1088/0741-3335/45/12A/019.

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 Creators:
Weller, A.1, Author           
Geiger, J.2, Author           
Werner, A.3, Author           
Zarnstorff, M. C.4, Author
Nührenberg, C.5, Author           
Sallander, E.1, Author           
Baldzuhn, J.6, Author           
Brakel, R.2, Author           
Burhenn, R.7, 8, Author           
Dinklage, A.2, Author           
Fredrickson, E.4, Author
Gadelmeier, F.6, Author           
Giannone, L.9, Author           
Grigull, P.3, Author           
Hartmann, D.10, Author           
Jaenicke, R.2, 8, Author           
Klose, S.11, 12, Author           
Knauer, J. P.6, Author           
Könies, A.5, Author           
Kolesnichenko, Ya. I.4, Author
Laqua, H. P.6, Author           Lutsenko, V. V.4, AuthorMcCormick, K.1, 8, Author           Monticello, D.4, AuthorOsakabe, M.4, AuthorPasch, E.13, Author           Reiman, A.4, AuthorRust, N.14, Author           Spong, D. A.4, AuthorWagner, F.2, Author           Yakovenko, Yu. V.4, AuthorW7-AS Team, Author   NBI-Group, Author   more..
Affiliations:
1Stellarator Scenario Development (E5), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856285              
2Experimental Plasma Physics 3 (E3), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856291              
3W7-X: Physics (PH), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856305              
4Princeton 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, ou_persistent22              
5Stellarator Theory (ST), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856287              
6External Organizations, ou_persistent22              
7VINETA, Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856311              
8W7-AS, Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856310              
9Experimental Plasma Physics 1 (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856295              
10Technology (TE), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856318              
11Plasma Diagnostics Group (HUB), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856324              
12Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856292              
13Stellarator Optimisation (E3), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856329              
14W7-X: Heating (HT), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856343              

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Free keywords: 30th European Physical Society Conference on Controlled Fusion and Plasma Physics, St. Petersburg, 2003-07-07 to 2003-07-01
 Abstract: 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.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Issued
 Pages: -
 Publishing info: -
 Table of Contents: -
 Rev. Type: Peer
 Degree: -

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Title: Invited papers from the 30th European Physical Society Conference on Controlled Fusion and Plasma Physics
Source Genre: Issue
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Publ. Info: -
Pages: - Volume / Issue: - Sequence Number: - Start / End Page: A285 - A308 Identifier: -

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Title: Plasma Physics and Controlled Fusion
  Alternative Title : Plasma Phys. Control. Fusion
Source Genre: Journal
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Publ. Info: Copyright © Institute of Physics and IOP Publishing Limited 2003
Pages: - Volume / Issue: 45 (A12) Sequence Number: - Start / End Page: - Identifier: -