| Autor: |
H.E. St. John, M. S. Chu, Farrokh Najmabadi, P. B. Snyder, T. K. Mau, Charles Kessel, A. D. Turnbull, R.J. LaHaye, Robert L. Miller, T.W. Petrie, W. P. West, G. M. Staebler, Vincent Chan, P. A. Politzer, Stephen Jardin, Lang L. Lao |
| Rok vydání: |
2006 |
| Předmět: |
|
| Zdroj: |
Fusion Engineering and Design. 80:25-62 |
| ISSN: |
0920-3796 |
| DOI: |
10.1016/j.fusengdes.2005.06.352 |
| Popis: |
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. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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