DocumentCode
2272515
Title
Toroidal magnetic confinement and coil power supplies in ITER
Author
Goff, Jeremy K. ; Casper, Thomas ; Murray, Stephen
Author_Institution
ITER Organ., St. Paul-lez-Durance, France
fYear
2011
fDate
20-23 Aug. 2011
Firstpage
1
Lastpage
5
Abstract
This paper outlines the principles of magnetic confinement of fusion plasma as implemented in the ITER device. The configuration of the magnet power supplies is described together with coil current scenarios for a typical plasma discharge.
Keywords
Tokamak devices; coils; discharges (electric); plasma toroidal confinement; power supplies to apparatus; ITER; coil current; fusion plasma; magnet power supplies; plasma discharge; toroidal magnetic confinement; Circuit faults; Coils; Discharges; Magnetic confinement; Superconducting magnets; Thyristors;
fLanguage
English
Publisher
ieee
Conference_Titel
Electrical Machines and Systems (ICEMS), 2011 International Conference on
Conference_Location
Beijing
Print_ISBN
978-1-4577-1044-5
Type
conf
DOI
10.1109/ICEMS.2011.6073414
Filename
6073414
Link To Document