Title :
Transport simulation of ITER startup
Author :
Attenberger, S.E. ; Houlberg, W.A.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
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;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102181
