Electromechanical analysis of the JET MkII-HD divertor

Author

Riccardo, V. ; Villedieu, E. ; Altmann, H. ; Starkey, D. ; Baker, R. ; Eagle, R. ; Macmillan, G.

Author_Institution

EURATOM-UKAEA Fusion Assoc., Abingdon, UK

fYear

2003

fDate

14-17 Oct. 2003

Firstpage

58

Lastpage

61

Abstract

The existing JET divertor will be modified to cope with the high power, high triangularity plasmas that will be run after the 2004 shutdown. The modified divertor, MkII HD, includes the design of the load bearing septum replacement tiles (LB-SRP), the high field side gap closure tiles (HFS-GC) and the refurbishment of several divertor diagnostics. Metallic carriers had to be introduced to interface the new rows of tiles with the existing carbon fiber composite base plates.

Keywords

Tokamak devices; carbon fibre reinforced composites; fusion reactor design; fusion reactor divertors; plasma toroidal confinement; plates (structures); C; JET MkII-HD divertor; carbon fiber composite base plates; divertor diagnostics; electromechanical analysis; high field side gap closure tiles; high triangularity plasmas; load bearing septum replacement tiles; metallic carriers; Coils; Current measurement; Eddy currents; High definition video; Magnetic analysis; Plasma diagnostics; Probes; Protection; Thermal loading; Tiles;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on

Print_ISBN

0-7803-7908-X

Type

conf

DOI

10.1109/FUSION.2003.1425877

Filename

1425877