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  Status of WENDELSTEIN 7-X construction

Wanner, M., Erckmann, V., Feist, J.-H., Gardebrecht, W., Hartmann, D., Krampitz, R., et al. (2003). Status of WENDELSTEIN 7-X construction. Nuclear Fusion, 43(6), 416-424. doi:10.1088/0029-5515/43/6/304.

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 Creators:
Wanner, M.1, Author              
Erckmann, V.2, Author              
Feist, J.-H.1, Author              
Gardebrecht, W.1, Author              
Hartmann, D.3, Author              
Krampitz, R.4, Author              
Niedermeyer, H.1, Author              
Renner, H.1, Author              
Rummel, T.1, Author              
Schauer, F.1, Author              
Wegener, L.1, Author              
Wesner, F.4, Author              
Müller, G. A.5, Author
Kasparek, W.5, Author
Thumm, M.5, Author
Dammertz, G.5, Author
Affiliations:
1W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856314              
2W7-X: Physics (PH), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856305              
3Technology (TE), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856318              
4External Organizations, ou_persistent22              
5Institut für Plasmaforschung, Universität Stuttgart, Pfaffenwaldring 31, D-70569 Stuttgart, Germany; Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft, EURATOM Association, Herrmann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany, ou_persistent22              

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 Abstract: WENDELSTEIN 7-X (W7-X) shall confirm the favourable plasma properties and the high density and beta limits of the helical advanced stellarator and demonstrate steady-state operation. The magnetic configuration of W7-X is characterized by a set of 50 non-planar and 20 planar superconducting coils. The magnet system will be manufactured and assembled to a precision of a few millimetres and maintain its symmetry during cool-down to cryogenic temperatures. Power supplies allows one to adjust the magnetic field with a precision of a few milli Tesla and safely dump the magnet energy in case of a quench. The plasma vessel gives maximum space for the plasma and is kept symmetrically with respect to the plasma by dedicated means. Steady-state heating is achieved by 10 MW ECRH. Energy and particles are controlled by a continuously working divertor. All plasma-facing surfaces are covered by CFC, graphite or B4C, respectively. The paper reviews the status of the construction and describes details of the design.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Published in print
 Pages: -
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 Table of Contents: -
 Rev. Type: Peer
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Title: Nuclear Fusion
  Alternative Title : Nucl. Fusion
Source Genre: Journal
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Publ. Info: Copyright © Institute of Physics and IOP Publishing Limited 2003
Pages: - Volume / Issue: 43 (6) Sequence Number: - Start / End Page: 416 - 424 Identifier: -