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Engineering Considerations of the Toroidal Magnet and Dewar for Uwmak-11—a Wisconsin Tokamak Fusion Reactor Design

  • I. N. Sviatoslavsky
  • W. C. Young
  • J. W. Lue
Part of the Advances in Cryogenic Engineering book series (ACRE, volume 21)

Abstract

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.

Keywords

Toroidal Field Lateral Support Neutral Beam Injector Cryogenic System Field Coil 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    W. C. Young and R. W. Boom, in: Proc. Fourth Intern. Conference on Magnet Technology, Brookhaven National Laboratory, New York (1972).Google Scholar
  2. 2.
    University of Wisconsin Fusion Feasibility Study Group, “UWMAK-II, A Conceptual Tokamak Reactor Design,” University of Wisconsin Rept. FDM-112 (June 1975).Google Scholar
  3. 3.
    W. C. Young and I. N. Sviatoslavsky, in: Proceedings of Fifth Intern. Conference on Magnet Technology, Rome, Italy (1975), p. 305.Google Scholar

Copyright information

© Springer Science+Business Media New York 1960

Authors and Affiliations

  • I. N. Sviatoslavsky
    • 1
  • W. C. Young
    • 1
  • J. W. Lue
    • 1
  1. 1.University of WisconsinMadisonUSA

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