DocumentCode
1063983
Title
Engineering and test of magnet systems for NET
Author
Salpietro, E.
Author_Institution
Max-Planck-Inst. fur Plasmaphys., Garching, West Germany
Volume
24
Issue
2
fYear
1988
fDate
3/1/1988 12:00:00 AM
Firstpage
1295
Lastpage
1298
Abstract
The magnetic system of NET (Next European Torus) provides a framework inside which ignited plasmas can be confined while nuclear component testing is performed. The toroidal and poloidal field coils are superconducting, since the demonstration of the applicability of this technology to a fusion reactor is an important part of the NET objectives. The toroidal field coils´ winding pack is made of double pancakes realized by winding the conductor with dry glass in the final shape. The poloidal field coils are divided into two subsets, the central solenoid stack and the outer equilibrium coils. Superficially both subsets are similar in that both will consist of a 40-kA force flow. He-cooled superconducting conductor in a glass-fiber-reinforced epoxy matrix, and perform both equilibrium and transformer functions. However, because of different operating conditions (field and stress levels), it is expected that the coils will use different conductor designs.
Keywords
Tokamak devices; fusion reactor theory and design; superconducting magnets; 40 kA; NET; conductor designs; equilibrium coils; fusion reactor; operating conditions; poloidal field coils; solenoid stack; superconducting magnet systems; test; toroidal field coils; transformer; winding pack; Conductors; Fusion reactors; Glass; Magnetic confinement; Performance evaluation; Plasma confinement; Superconducting coils; Superconducting magnets; System testing; Toroidal magnetic fields;
fLanguage
English
Journal_Title
Magnetics, IEEE Transactions on
Publisher
ieee
ISSN
0018-9464
Type
jour
DOI
10.1109/20.11475
Filename
11475
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