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.
fDate :
7/1/1996 12:00:00 AM
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;
Journal_Title :
Magnetics, IEEE Transactions on
