Physics basis for the advanced tokamak fusion power plant, ARIES-AT

• Published in: Fusion engineering and design 2006, Vol.80 (1), p.25-62
• Main Authors: Jardin, S.C., Kessel, C.E., Mau, T.K., Miller, R.L., Najmabadi, F., Chan, V.S., Chu, M.S., LaHaye, R., Lao, L.L., Petrie, T.W., Politzer, P., St.John, H.E., Snyder, P., Staebler, G.M., Turnbull, A.D., West, W.P.
• Format: Article
• Language: English
• Subjects: Advanced tokamak; Fusion power plant; Physics basis; Reactor studies
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2005.06.352

The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A ≡ R / a = 4.0 , an elongation and triangularity of κ = 2.20 , δ = 0.90 (evaluated at the separatrix surface), a toroidal beta of β = 9.1 % (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of β N ≡ 100 × β / ( I P ( M A ) / 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 f BS ≡ I BS / I P = 0.91 . This leads to a design with total plasma current I P = 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. 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.