Doublet III Big Dee Project
The Doublet III tokamak is presently being reconfigured into a new larger dee-shaped plasma configuration. Experiments will begin in 1986 with a goal of high current, high beta plasma operation at moderate magnetic field. The existing toroidal field coil, Ohmic heating coil, and innermost plasma shaping coils will be retained. A new water-cooled vacuum vessel is being fabricated using a corrugated Inconel sandwich wall construction. Six new water-cooled copper poloidal field coils are also being fabricated. The resultant device along with additional power supplies will provide a capability for plasma currents of 3.5 MA for 1.5 s during the first phase of operations; the tokamak systems are designed for 5 MA operation with additional power systems. The four existing 80 keV, 3 MW neutral beam lines are being modified for optimum torus access and 0.7 s operation. These injectors will be upgraded to allow 5 s operation with new sources in 1987. The device has been designed to accommodate an additional 20 MW of ICRH and ECH power in the future. Limiters and vessel wall protection will be provided for initial operation with up to 40 MJ of input energy. Future installation of additional thermal armor will allow operation with up to 200 MJ of input energy over a 10 s period. Most of the existing diagnostics will be modified as required and reinstalled on the new vessel.
- Research Organization:
- GA Technologies Inc., San Diego, California 92138
- DOE Contract Number:
- AC03-84ER51044
- OSTI ID:
- 5539341
- Journal Information:
- J. Vac. Sci. Technol., A; (United States), Vol. 3:3
- Country of Publication:
- United States
- Language:
- English
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