L-H Threshold Studies in NSTX

Kaye, S. M. ; Battaglia, D. ; Bell, R. E. ; Chang, C. S. ; Hosea, J. ; Kugel, H. ; LeBlanc, B. P. ; Meyer, H. ; Park, G. Y.

Princeton University. Plasma Physics Laboratory.

关键词: 70 Plasma Physics And Fusion Technology;    Deuterium;    Plasma;    Confinement;    H-Mode Plasma Confinement, Tokamaks, Nstx;   

DOI  :  10.2172/1028184
RP-ID  :  PPPL-4635
RP-ID  :  DE-ACO2-09CH11466
RP-ID  :  1028184

美国|英语

来源: UNT Digital Library

【 摘 要 】

Recent experiments in the low aspect ratio National Spherical Torus Experiment (NSTX) have been run in support of the high priority ITER and ITPA issue of access to the H-mode. Specifically, a series of experiments showed reduced power threshold values for deuterium vs helium plasmas, and for plasmas with lower current, lower triangularity and with lithium conditioning. Application of n=3 fields at the plasma edge resulted in higher power thresholds. To within the constraints of temporal and spatial resolutions, no systematic difference in T{sub e}, n{sub e}, p{sub e}, T{sub i}, v or their derivatives was found in discharges that transitioned into the H-mode versus those at slightly lower power that did not. Finally, H{sub 98y,2} {approx} 1 confinement quality could be achieved for powers just above the threshold power in ELM-free conditions.