Designing and manufacturing of the coil support structure of W7-X

Wendelstein 7-X (W7-X) is a fully optimized low-shear stellarator and shall demonstrate the reactor potential of this fusion plant. It is presently under construction at the Greifswald Branch Institute of IPP. The superconducting magnet system will allow continuous operation, limited only by the pla...

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Bibliographic Details
Published in:Fusion engineering and design 2009-06, Vol.84 (2), p.578-585
Main Authors: Chauvin, Didier, Koppe, Torsten, Cardella, Antonio, Missal, Bernd, Pilopp, Dirk, Reich, Jens, Di Bartolo, Giovanni, Camin, Rocio, Gonzales, Ivan, Giordano, Luca, Langone, Stefano
Format: Article
Language:English
Subjects:
Applied sciences
Coil support structure (CSS)
Coiling
Construction
Controled nuclear fusion plants
Design
Devices
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Flanges
Half module (HM)
Installations for energy generation and conversion: thermal and electrical energy
Manufacturing
Modules
Polypropylenes
Process
Project management
Reactors
Supports
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Summary:Wendelstein 7-X (W7-X) is a fully optimized low-shear stellarator and shall demonstrate the reactor potential of this fusion plant. It is presently under construction at the Greifswald Branch Institute of IPP. The superconducting magnet system will allow continuous operation, limited only by the plasma exhaust system whose capacity is designed for 30 min full power operation. The Wendelstein 7-X (W7-X) coils and structures are part of the largest superconducting fusion device being constructed at present. They represent a technical challenge at industrial level and the need for proven techniques and manufacturing processes in accordance to the highest quality standards. The production of these components requires a management of monitoring for quality and tests. The coil system consists of 20 planar and 50 non-planar coils. They are supported by a pentagonal 10 m diameter, 2.5 m high coil support structure (CSS). The CSS is divided into five modules. Each module consists of two equal half modules. The manufacturing status of the CSS and the main project management and technical challenges will be presented. The lessons learned in the large scale production of this difficult kind of support structure will be presented as relevant experience for the realization of similar systems for future fusion devices, such as ITER.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2009.03.018