Core Fueling and Edge Particle Flux Analysis in Ohmically and Auxiliary Heated NSTX Plasmas

Soukhanovskii, V.A. ; Maingi, R. ; Raman, R. ; Kugel, H.W. ; LeBlanc, B.P. ; Roquemore, L. ; Skinner, C.H. ; Team, NSTX Research

Princeton University. Plasma Physics Laboratory.

关键词: Beam Injection;    70 Plasma Physics And Fusion Technology;    Divertors;    Particle Sources;    Optimization;   

DOI  :  10.2172/798192
RP-ID  :  PPPL-3704.pdf
RP-ID  :  AC02-76CH03073
RP-ID  :  798192

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Boundary Physics program of the National Spherical Torus Experiment (NSTX) is focusing on optimization of the edge power and particle flows in b * 25% L- and H-mode plasmas of t {approx} 0.8 s duration heated by up to 6 MW of high harmonic fast wave and up to 5 MW of neutral beam injection. Particle balance and core fueling efficiencies of low and high field side gas fueling of L-mode homic and NBI heated plasmas have been compared using an analytical zero dimensional particle balance model and measured ion and neutral fluxes. Gas fueling efficiencies are in the range of 0.05-0.20 and do not depend on discharge magnetic configuration, density or poloidal location of the injector. The particle balance modeling indicates that the addition of HFS fueling results in a reversal of the wall loading rate and higher wall inventories. Initial particle source estimates obtained from neutral pressure and spectroscopic measurements indicate that ion flux into the divertor greatly exceeds midplane ion flux from the main plasma, suggesting that the scrape-off cross-field transport plays a minor role in diverted plasmas. Present analysis provides the basis for detailed fluid modeling of core and edge particle flows and particle confinement properties of NSTX plasmas. This research was supported by the U.S. Department of Energy under contracts No. DE-AC02-76CH03073, DE-AC05-00OR22725, and W-7405-ENG-36.