Title :
Plasma shape control calculations for BPX divertor design
Author :
Strickler, D.J. ; Neilson, G.H. ; Jardin, S.C. ; Pomphrey, N.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
fDate :
30 Sep-3 Oct 1991
Abstract :
A control matrix MHD (magnetohydrodynamic) equilibrium code, BEQ, and the Tokamak Simulation Code (TSC) are used to compute programmed double-null (DN) divertor sweep trajectories that maximize sweep distance while simultaneously satisfying a set of strict constraints: minimum lengths of the field lines between the X-point and strike points, minimum spacing between the inboard plasma edge and the limiter, maximum spacing between the outboard plasma edge and the ICRF (ion cyclotron range of frequencies) antennas, minimum safety factor, and linked poloidal flux. A sequence of DN diverted equilibria and a consistent TSC fiducial discharge simulation are used in evaluating the performance of the BPX (Burning Plasma Experiment) divertor shape and possible modifications
Keywords :
fusion reactor ignition; fusion reactor theory and design; nuclear engineering computing; plasma magnetohydrodynamics; plasma radiofrequency heating; plasma simulation; plasma toroidal confinement; BEQ; BPX divertor design; Burning Plasma Experiment; ICRF; TSC; Tokamak Simulation Code; X-point; antennas; control matrix MHD; discharge simulation; divertor sweep trajectories; equilibrium code; field lines; inboard plasma edge; ion cyclotron range of frequencies; limiter; linked poloidal flux; magnetohydrodynamic; minimum lengths; minimum safety factor; minimum spacing; modifications; programmed double-nul; shape control calculations; strike points; Coils; Computational modeling; Geometry; Laboratories; Magnetohydrodynamics; Physics; Plasma diagnostics; Plasma measurements; Plasma simulation; Shape control;
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
DOI :
10.1109/FUSION.1991.218694
