Engineering Considerations of the Toroidal Magnet and Dewar for Uwmak-11—a Wisconsin Tokamak Fusion Reactor Design
Optimization studies seem to indicate that a typical Tokamak power reactor will have a thermal output of 5000 MW, a major radius of 13 m, and a minor radius of 5 m. The D-shaped superconductive toroidal field magnets for such a reactor will probably have a bore of 25 m. Radiation damage to the plasma containment vessel will require its periodic replacement by remote control. This implies that the magnets should be easily removed from the reactor, or alternatively, be large enough to allow sections of the containment vessel to be removed from within their enclosure.
KeywordsToroidal Field Lateral Support Neutral Beam Injector Cryogenic System Field Coil
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