The ASDEX upgrade TF coils: design to acceptance

Author

Streibl, B. ; Zeisberg, A. ; Gagliardi, P.

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

1248

Lastpage

1251

Abstract

The design essentials of the toroidal-field (TF) coils for ASDEX upgrade (AU) are summarized. The AU tokamak is a fusion experiment with a poloidal divertor. Its main goals are to simulate reactor-type plasma-wall interaction with a magnetic-field configuration compatible with reactor requirements, i.e. the poloidal field (PF) and control coils outside the TF coils. The resulting plasma cross sections of the single- (SN) and double- (DN) divertor configurations are highly elongated in this case. Consequently, the familiar constant-tension D-shape was chosen for the TF coils to produce at the plasma center a flux density of up to 4 T. Stress computations and mechanical testing are also reviewed and the manufacturing experience gained from three completed and five assembled coils is sketched.

Keywords

Tokamak devices; fusion reactor theory and design; plasma confinement; ASDEX upgrade TF coils; AU tokamak; assembled coils; constant-tension D-shape; control coils; design essentials; design to acceptance; divertor configurations; flux density; magnetic-field configuration; manufacturing experience; mechanical testing; plasma cross sections; poloidal divertor; simulate reactor-type plasma-wall interaction; stress computations; toroidal field coils; Coils; Fusion reactor design; Gold; Inductors; Magnetic flux; Plasma density; Plasma simulation; Tokamaks; Toroidal magnetic fields; Variable speed drives;

fLanguage

English

Journal_Title

Magnetics, IEEE Transactions on

Publisher

ieee

ISSN

0018-9464

Type

jour

DOI

10.1109/20.11462

Filename

11462