Transport simulation of ITER startup

Author

Attenberger, S.E. ; Houlberg, W.A.

Author_Institution

Oak Ridge Nat. Lab., TN, USA

fYear

1989

fDate

2-6 Oct 1989

Firstpage

99

Abstract

The present International Thermonuclear Experimental Reactor (ITER) reference configurations are provided by the technology phase, in which the plasma current is maintained noninductively at a subignition density, and the physics phase, which is ignited but requires inductive maintenance of the current. The WHIST 1.5-D transport code is used to evaluate the volt-second requirements of both configurations. A slow current ramp (60-80 s) is required for fixed-radius startup in the ITER to avoid hollow current density profiles. Reaching the operating point requires about 203 V-s for the technology phase (18 MA), and about 270 V-s for the physics phase (22 MA). The resistive losses can be reduced with expanding-radius startup

Keywords

Tokamak devices; fusion reactor ignition; fusion reactor theory and design; plasma production; plasma toroidal confinement; plasma transport processes; ITER; International Thermonuclear Experimental Reactor; WHIST 1.5-D transport code; fixed-radius startup; hollow current density profiles; plasma current; resistive losses; subignition density; volt-second requirements; Current density; Magnetic confinement; Magnetic flux; Maintenance engineering; Physics; Plasma confinement; Plasma density; Plasma simulation; Plasma temperature; Plasma transport processes;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on

Conference_Location

Knoxville, TN

Type

conf

DOI

10.1109/FUSION.1989.102181

Filename

102181