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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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Wanner, M.1, Autor           
Erckmann, V.2, Autor           
Feist, J.-H.1, Autor           
Gardebrecht, W.1, Autor           
Hartmann, D.3, Autor           
Krampitz, R.4, Autor           
Niedermeyer, H.1, Autor           
Renner, H.1, Autor           
Rummel, T.1, Autor           
Schauer, F.1, Autor           
Wegener, L.1, Autor           
Wesner, F.4, Autor           
Müller, G. A.5, Autor
Kasparek, W.5, Autor
Thumm, M.5, Autor
Dammertz, G.5, Autor
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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 Zusammenfassung: 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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Sprache(n): eng - English
 Datum: 2003
 Publikationsstatus: Erschienen
 Seiten: -
 Ort, Verlag, Ausgabe: -
 Inhaltsverzeichnis: -
 Art der Begutachtung: Expertenbegutachtung
 Art des Abschluß: -

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Titel: Nuclear Fusion
  Alternativer Titel : Nucl. Fusion
Genre der Quelle: Zeitschrift
 Urheber:
Affiliations:
Ort, Verlag, Ausgabe: Copyright © Institute of Physics and IOP Publishing Limited 2003
Seiten: - Band / Heft: 43 (6) Artikelnummer: - Start- / Endseite: 416 - 424 Identifikator: -