Confinement Studies of Auxiliary Heated NSTX Plasmas
Authors: B.P. LeBlanc, M.G. Bell, R.E. Bell, M.L. Bitter, C. Bourdelle, D.A. Gates, S.M. Kaye, R. Maingi, J.E. Menard, D. Mueller, S.F. Paul, A.L. Roquemore, A. Rosenberg, S.A. Sabbagh, D. Stutman, E.J. Synakowski, V.A. Soukhanovskii, J.R.Wilson and the NSTX Research Team
Date of PPPL Report: May 2003
Submitted to: Nuclear Fusion
The confinement of auxiliary heated NSTX discharges is discussed. The energy confinement time in plasmas with either L-mode or H-mode edges is enhanced over the values given by the ITER97L and ITER98Pby(2) scalings, being up to 2-3 times L-mode and 1.5 times H-mode. TRANSP calculations based on the kinetic profile measurements reproduce the magnetics-based determination of stored energy and the measured neutron production rate. Power balance calculations reveal that, in a high power neutral beam heated H-mode discharge, the ion thermal transport is near neoclassical levels, and well below the electron thermal transport, which is the main loss channel. Perturbative impurity injection techniques indicate the particle diffusivity to be slightly above the neoclassical level in discharges with L-mode edge. High-harmonic fast-wave (HHFW) bulk electron heating is described and thermal transport is discussed. Thermal ion transport is found to be above neoclassical level, but thermal electron transport remains the main loss mechanism. Evidences of an electron thermal internal transport barrier obtained with HHFW heating are presented. A description of H-mode discharges obtained during HHFW heating is presented.