Abstract
The toroidal field (TF) magnets of the conceptual designs for tokamak fusion reactors performed at the (University of Wisconsin [1], called UWMAK consist of solid coils bolted together to form constant-tension D-shaped structures. Each coil consists of a forged or extruded helically grooved, solid, D-shaped disk of stainless steel or aluminum alloy. The conductor (see Fig. 1) is insulated with epoxy-impregnated fiberglass tape, and embedded in the grooves on both sides of the disk. After oven curing, the fiberglass on the exposed surface of the conductor is machined off for better cooling in a pool of liquid helium. The coils are separated with Micarta spacers to allow free movement of the coolant throughout the structure.
Supported by the Division of Magnetic Fusion Energy of the U.S. Energy Research and Development Administration.
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References
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P. Hwang, University of Wisconsin, Madison, Wisconsin, private communication.
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Hong, S.O., Michaelson, P.F., Sviatoslavsky, I.N., Young, W.C. (1978). Resistance to Strain Degradation in Preliminary UWMAK TF Coil Conductors for Fusion Reactors. In: Timmerhaus, K.D., Reed, R.P., Clark, A.F. (eds) Advances in Cryogenic Engineering. Advances in Cryogenic Engineering, vol 24. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-9853-0_37
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DOI: https://doi.org/10.1007/978-1-4613-9853-0_37
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