Prepared for the U.s. Department of Energy, under Contract De-ac02-76ch03073 Princeton Plasma Physics Laboratory Princeton University, Princeton, New Jersey

نویسندگان

  • F. Najmabadi
  • C. E. Kessel
  • T. K. Mau
  • S. C. Jardin
چکیده

An advanced tokamak plasma con guration is developed based on equilibrium, ideal MHD stability, bootstrap current analysis, vertical stability and control, and poloidal eld coil analysis. The plasma boundaries used in the analysis are forced to coincide with the 99% ux surface from the freeboundary equilibrium. Using an accurate bootstrap current model and external current drive pro les from ray tracing calculations in combination with optimized pressure pro les, N values above 7.0 have been obtained. The minimum current drive requirement is found to lie at a lower N of 5.4. The external kink mode is stabilized by a tungsten shell located at 0.33 times the minor radius and a feedback system. Plasma shape optimization has led to an elongation of 2.2 and triangularity of 0.9 at the separatrix. Vertical stability could be achieved by a combination of tungsten shells located at 0.33 times the minor radius and feedback control coils located behind the shield. The poloidal eld coils were optimized in location and current, providing a maximum coil current of 8.6 MA. These developments have led to a simultaneous reduction in the power plant major radius and toroidal eld.

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تاریخ انتشار 2001