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Status of WENDELSTEIN 7-X construction

MPS-Authors
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Wanner,  M.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Erckmann,  V.
W7-X: Physics (PH), Max Planck Institute for Plasma Physics, Max Planck Society;

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Feist,  J.-H.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Gardebrecht,  W.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Hartmann,  D.
Technology (TE), Max Planck Institute for Plasma Physics, Max Planck Society;

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Niedermeyer,  H.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Renner,  H.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Rummel,  T.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Schauer,  F.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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Wegener,  L.
W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society;

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引用

Wanner, M., Erckmann, V., Feist, J.-H., Gardebrecht, W., Hartmann, D., Krampitz, R., Niedermeyer, H., Renner, H., Rummel, T., Schauer, F., Wegener, L., Wesner, F., Müller, G. A., Kasparek, W., Thumm, M., & Dammertz, G. (2003). Status of WENDELSTEIN 7-X construction. Nuclear Fusion, 43(6), 416-424. doi:10.1088/0029-5515/43/6/304.


引用: https://hdl.handle.net/11858/00-001M-0000-0027-2F2D-E
要旨
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.