Title :
Equilibrium shape control in CIT PF design
Author :
Strickler, D.J. ; Pomphrey, N. ; Jardin, S.C.
Author_Institution :
Fusion Eng. Design Center, Oak Ridge Nat. Lab., TN, USA
Abstract :
The free-boundary equilibrium code VEQ provides equilibrium data that are used by the Tokamak Simulation Code (TSC) in designing and analyzing the poloidal-field (PF) system for the Compact Ignition Tokamak (CIT). VEQ serves as an important design tool for locating the PF coils and defining coil current trajectories and control systems for the TSC. VEQ and its role in the TSC analysis of the CIT PF system are described
Keywords :
coils; fusion reactor theory and design; nuclear engineering computing; CIT; Compact Ignition Tokamak; Tokamak Simulation Code; VEQ; coil current trajectories; control systems; equilibrium shape control; free-boundary equilibrium code; poloidal field system; Coils; Control systems; Design engineering; Laboratories; Packaging; Physics; Plasma applications; Plasma simulation; Plasma transport processes; Shape control;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102363
