Gyrokinetic Calculations of Microturbulence and Transport for NSTX and Alcator-CMOD H-modes

Redi, M.H. ; Dorland, W. ; Bell, R. ; Bonoli, P. ; Bourdelle, C. ; Candy, J. ; Ernst, D. ; Fiore, C. ; Gates, D. ; Hammett, G. ; Hill, K. ; Kaye, S. ; LeBlanc, B. ; Menard, J. ; Mikkelsen, D. ; Rewoldt, G. ; Rice, J. ; Waltz, R. ; Wukitch, S.

Princeton University. Plasma Physics Laboratory.

关键词: Heating;    Tokamak;    70 Plasma Physics And Fusion Technology;    Transport Tokamak;    Spherical Torus;   

DOI  :  10.2172/814699
RP-ID  :  PPPL-3834
RP-ID  :  AC02-76CH03073
RP-ID  :  814699

美国|英语

来源: UNT Digital Library

【 摘 要 】

Recent H-mode experiments on NSTX [National Spherical Torus Experiment] and experiments on Alcator-CMOD, which also exhibit internal transport barriers (ITB), have been examined with gyrokinetic simulations with the GS2 and GYRO codes to identify the underlying key plasma parameters for control of plasma performance and, ultimately, the successful operation of future reactors such as ITER [International Thermonuclear Experimental Reactor]. On NSTX the H-mode is characterized by remarkably good ion confinement and electron temperature profiles highly resilient in time. On CMOD, an ITB with a very steep electron density profile develops following off-axis radio-frequency heating and establishment of H-mode. Both experiments exhibit ion thermal confinement at the neoclassical level. Electron confinement is also good in the CMOD core.