Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT

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. ; John, H.E. St. ; Snyder, P. ; Staebler, G.M. ; Turnbull, A.D. ; West, W.P.

Princeton University. Plasma Physics Laboratory.

关键词: Bootstrap Current;    70 Plasma Physics And Fusion Technology;    Stability Fusion Reactions, Low Temperature;    Elongation;    Fusion Reactions, Low Temperature;   

DOI  :  10.2172/820081
RP-ID  :  PPPL-3878
RP-ID  :  AC02-76CH03073
RP-ID  :  820081

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来源: UNT Digital Library

【 摘 要 】

The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A always equal 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 * 100 x b/(I(sub)P(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 * I(sub)BS/I(sub)P = 0.91. This leads to a design with total plasma current I(sub)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, 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. Tran sport 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.