Title :
Plasma stability and confinement in the PBX-M tokamak
Abstract :
Summary form only given. The PBX-M physics program exploits strong plasma shaping, control of the pressure and current profiles, and a close-fitting conducting wall for the understanding and optimization of plasma stability and confinement. Transport studies and ITER and CIT R&D-relevant studies of high-performance plasmas have focused on: (1) high-beta (⟨β⟩~6.8%) plasma with good energy confinement and high-temperature; (2) high-beta relative to the Troyon limit: (3) highly-indented (i~30%) plasmas. using plasma current ramps to drive the necessary edge current; (4) H-mode phases in both limited and diverted discharges; (5) current profile control by current ramping, counterneutral beam injection, and pellet injection: (6) development of j(r) diagnostics and initial studies of q(r) effects on sawteeth and fishbones: (7) modifications of disruption precursor growth rates and mode structure; and (8) disruptive vertical displacement events
Keywords :
optimisation; plasma diagnostics; plasma instability; plasma toroidal confinement; plasma transport processes; CIT; H-mode phases; ITER; PBX-M tokamak; Troyon limit; close-fitting conducting wall; counterneutral beam injection; current profile control; current ramping; disruption precursor growth rates; disruptive vertical displacement events; diverted discharges; edge current; energy confinement; high-beta; high-performance plasmas; high-temperature; highly indented plasmas; j(r) diagnostics; mode structure; optimization; pellet injection; plasma current ramps; plasma shaping; plasma stability; pressure control; q(r) effects; sawteeth; toroidal confinement; transport;
Conference_Titel :
Plasma Science, 1990. IEEE Conference Record - Abstracts., 1990 IEEE International Conference on
Conference_Location :
Oakland, CA, USA
DOI :
10.1109/PLASMA.1990.110599
