DocumentCode
1086056
Title
Design of the outer poloidal field coil system for ITER
Author
Yoshida, K. ; Shimada, M. ; Matsukawa, M. ; Sborchia, C. ; Stepanov, B. ; Stoner, J. ; Nozawa, M.
Volume
32
Issue
4
fYear
1996
fDate
7/1/1996 12:00:00 AM
Firstpage
2240
Lastpage
2243
Abstract
The ITER poloidal field (PF) coil system consists of a central solenoid coil and seven ring coils. The PF coils must provide the magnetic fields to confine the plasma and control its position during the various phase of operation including plasma initiation, ramp-up, burn and shut-down. They contribute the magnetic flux change to ramp up the plasma current and a part of the flux change to maintain it. This paper describes the requirements and the conceptual design for the seven outer PF coils
Keywords
fusion reactor design; fusion reactor materials; magnetic fields; magnetic flux; plasma confinement; solenoids; superconducting coils; superconducting magnets; ITER poloidal field coil; burn; conceptual design; magnetic fields; magnetic flux change; outer superconducting field coils; plasma confinement; plasma initiation; ramp-up; shut-down; Electric breakdown; Magnetic confinement; Magnetic flux; Plasma confinement; Solenoids; Superconducting cables; Superconducting coils; Superconducting magnets; Toroidal magnetic fields; Voltage;
fLanguage
English
Journal_Title
Magnetics, IEEE Transactions on
Publisher
ieee
ISSN
0018-9464
Type
jour
DOI
10.1109/20.508611
Filename
508611
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