An Optimized Central Solenoid for ITER

Author

Libeyre, P. ; Beemsterboer, C. ; Bessette, D. ; Gribov, Y. ; Jong, C. ; Lyraud, C. ; Dolgetta, N. ; Mitchell, N. ; Vollmann, T.

Author_Institution

ITER Organ., St. Paul-lez-Durance, France

Volume

20

Issue

3

fYear

2010

fDate

6/1/2010 12:00:00 AM

Firstpage

398

Lastpage

401

Abstract

The Central Solenoid (CS) of the ITER tokamak has to provide the flux variation needed to induce the plasma current and to shape the field lines in the divertor region. It is designed as a stack of 6 identical coils, independently power supplied. Repulsing forces arising between the coils during a scenario are withstood by a precompression structure installed around the coils. Studies were carried out to simplify the winding manufacture, to optimize the precompression structure and procedure, to optimize the stack assembly of the 6 coils and the assembly of the central solenoid inside the tokamak which allows withdrawal from the machine, while meeting the ITER design criteria and in particular the Magnet Structural Design Criteria (static and fatigue).

Keywords

Tokamak devices; fusion reactor design; plasma toroidal confinement; superconducting magnets; ITER tokamak; Magnet Structural Design Criteria; divertor region; flux variation; identical coils; optimized central solenoid; plasma current; precompression structure; superconducting magnets; winding manufacture; Central solenoid; ITER; design; precompression structure; superconducting magnets;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2010.2041639

Filename

5433240