Analysis of the poloidal field system leads in the IGNITEX experiment

Author

Montalvo, E. ; Carrera ; Dong, J. ; Driga, M. ; Hsieh, K. ; Walls, A. ; Weldon, W.

Author_Institution

Texas Univ., Austin, TX, USA

fYear

1989

fDate

2-6 Oct 1989

Firstpage

858

Abstract

Some aspects of the operation of the poloidal-field (PF) system of the Fusion Ignition Experiment (IGNITEX) are analyzed. Stresses in the PF system due to the poloidal magnetic field are calculated for unsupported coils. When the structural eddy currents are taken into account, the stresses are considerably reduced. Stresses in the PF terminals due to the toroidal magnetic field are calculated for a terminal partially supported by the toroidal-field (TF) magnet. The maximum stresses occur in the lead located in the TF inner leg at the end of the flat top of the discharge. Stresses in the PF coils and the PF terminals are tolerable. A preliminary estimate of the perturbed vacuum magnetic field at breakdown is done, providing insight for the detailed design of the PF terminals

Keywords

eddy currents; fusion reactor ignition; fusion reactor operation; fusion reactor theory and design; Fusion Ignition Experiment; IGNITEX experiment; PF system; PF terminals; TF inner leg; breakdown; discharge; flat top; operation; perturbed vacuum magnetic field; poloidal field system leads; poloidal magnetic field; stresses; structural eddy currents; toroidal magnetic field; unsupported coils; Boring; Coils; Eddy currents; Fault location; Heating; Plasmas; Stress; Tokamaks; Toroidal magnetic fields; Vacuum breakdown;

fLanguage

English

Publisher

ieee

Conference_Titel

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

Conference_Location

Knoxville, TN

Type

conf

DOI

10.1109/FUSION.1989.102353

Filename

102353