Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT
Authors: S.C. Jardin, C.E. Kessel, T.K. Mau, R.L. Miller, F. Najmabadi, V.S. Chan, M.S. Chu, R. LaHaye, L.L. Lao, T.W. Petrie, P. Politzer, H.E. St. John, P. Snyder, G.M. Staebler, A.D. Turnbull, and W.P. West
Date of PPPL Report: October 2003
Submitted to: Fusion Engineering and Design
The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A equivalent to R/a = 4.0, an elongation and triangularity of kappa = 2.20, delta = 0.90 (evaluated at the separatrix surface), a toroidal beta of beta = 9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of bN equivalent to 100 x b/(IP(MA)/a(m)B(T) = 5.4. These beta values are chosen to be 10% below the ideal-MHD stability limit. The bootstrap-current fraction is fBS equivalent to IBS/IP = 0.91. This leads to a design with total plasma current IP = 12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m, respectively. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current-drive system consists of ICRF/FW for on-axis current drive and a lower-hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.