R. A. Bolton, L. Bromberg, D. I. Brown, U. R. Christensen, D. L. Jassby, M. Okabayashi, C. E. Singer

Research output: Contribution to conferencePaper


Up to 70% of the plasma current in large tokamak devices can be induced by the flux swing of the equilibrium field (EF), if the plasma pressure is increased very early during start-up and maintained at the MHD-limiting value throughout the current rise. In an illustration of this technique, a 4. 4-MA plasma current is induced by the EF coils assisted by a set of ″leaky OH″ coils and a small central solenoid. In a second example, current induction by the EF is supplemented by a 2. 0-MA neutral-beam-driven current, and the central transformer is eliminated entirely. A hybrid coil is described, wherein the TF and OH coils are merged into a single winding with greatly reduced net forces. These techniques can alleviate space restriction near the major axis in small-R tokamak reactors.

Original languageEnglish (US)
StatePublished - 1978
Event1978 American Nuclear Society Topical Meeting - Santa Fe, United States
Duration: May 9 1978May 11 1978
Conference number: 3


Conference1978 American Nuclear Society Topical Meeting
CountryUnited States
CitySanta Fe

ASJC Scopus subject areas

  • Engineering(all)

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    Bolton, R. A., Bromberg, L., Brown, D. I., Christensen, U. R., Jassby, D. L., Okabayashi, M., & Singer, C. E. (1978). NEW TECHNIQUES FOR INDUCING PLASMA CURRENT IN LARGE TOKAMAK DEVICES.. Paper presented at 1978 American Nuclear Society Topical Meeting, Santa Fe, United States.