Shape Optimization for DIII-D Advanced Tokamak Plasmas

Kesse, C.E. ; Ferron, J.R. ; Greenfield, C.M. ; Menard, J.E. ; Taylor, T.S.

Princeton University. Plasma Physics Laboratory.

关键词: Equilibrium, Mhd-Toroidal;    Tokamaks;    70 Plasma Physics And Fusion Technology;    Doublet-3 Device;    Elongation;   

DOI  :  10.2172/814731
RP-ID  :  PPPL-3848
RP-ID  :  AC02-76CH03073
RP-ID  :  814731

美国|英语

来源: UNT Digital Library

【 摘 要 】

The advanced tokamak program on DIII-D is targeting the full integration of high-beta and high-bootstrap/noninductive current fraction for long-pulse lengths and the high confinement consistent with these features. Central to achieving these simultaneously is access to the highest ideal beta limits possible to maximize the headroom for experimental operation with RWM control. A study of the ideal-MHD stability is done for plasmas modeled after DIII-D advanced tokamak plasmas, varying the plasma elongation, triangularity, and outboard squareness. The highest beta(sub)N limits reach 6-7 for the n=1 kink mode for all elongation, outer squareness values, and plasma triangularity equals 0.8.