The compact ignition tokamak (CIT)

R. D. Stambaugh, G. Bateman, M. G. Bell, D. Cohn, P. Colestock, Robert James Goldston, S. C. Jardin, J. Johnson, G. H. Neilson, M. Porkolab, J. A. Schmidt, D. J. Sigmar, M. Ulrickson, K. M. Young

Research output: Contribution to conferencePaperpeer-review

Abstract

Summary form only given. The Compact Ignition Tokamak (CIT) experiment is designed to establish the scientific feasibility of power production from the fusion process and to establish the basis of alpha particle physics for follow-on steps toward a magnetic confinement fusion reactor. The present design incorporates all those features which have been shown to improve tokamak performance. Since both the tokamak energy confinement and beta limit have been shown to be proportional to plasma current, CIT will operate at a high plasma current, Ip = 12.3 MA. A vertically elongated (κ = 2.0) double-null divertor plasma cross section was chosen to allow high Ip per unit toroidal field and to allow access to optimal tokamak confinement regimes. The high toroidal magnetic field BT = 11 T and compact size (R = 2.14 m, a = 0.66 m) are chosen within the constraints of allowable stress limits to support the high plasma current and reach ignition in a modest size and cost device. As its research program unfolds, CIT will progressively work through the physics issues of burning, alpha-heated plasmas to provide the information necessary for future devices.

Original languageEnglish (US)
Pages111-112
Number of pages2
StatePublished - Dec 1 1990
Externally publishedYes
Event1990 IEEE International Conference on Plasma Science - Oakland, CA, USA
Duration: May 21 1990May 23 1990

Other

Other1990 IEEE International Conference on Plasma Science
CityOakland, CA, USA
Period5/21/905/23/90

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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