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Current, temperature, and confinement time scaling in toroidal reversed-field pinch experiments ZT-I and ZT-S [electronic resource].

Published
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1976.
Physical Description
Pages: 10 : digital, PDF file
Additional Creators
United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The scaling properties of a toroidal reversed-field Z pinch have been investigated over a limited range by comparing two experiments having conducting walls and discharge tube minor diameters which differ by a factor of approximately 1.5. Both the confinement time of the plasma column and the electron temperature were found to increase about a factor of two with the increased minor diameter. Both the poloidal field diffusion and the decay of the toroidal reversed-field were significantly reduced with the larger tube diameter. These results support the hypothesis that the loss of stability later in the discharge is caused by diffusion induced deterioration of initially favorable plasma-field profiles to MHD unstable ones. This conclusion has been verified by stability analysis of the magnetic field profiles. Fusion reactor calculations show that small reactors are conceptually possible assuming good containment can be achieved for current densities greater than or equal to 20 MA/m/sup 2/.
Report Numbers
E 1.99:la-ur-76-1875
E 1.99: conf-761012-6
E 1.99: iaea-cn-35/e-1
iaea-cn-35/e-1
conf-761012-6
la-ur-76-1875
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Note
Published through SciTech Connect.
01/01/1976.
"la-ur-76-1875"
" conf-761012-6"
" iaea-cn-35/e-1"
6. international conference on plasma physics and controlled nuclear fusion research, Berchtesgaden, F.R. Germany, 6 Oct 1976.
Baker, D.A.; Hagenson, R.L.; Howell, R.B.; Burkhardt, L.C.; Di Marco, J.N.; Haberstich, A.; Karr, H.J.; Schofield, A.E.
Los Alamos Scientific Lab., N.Mex. (USA)
Funding Information
W-7405-ENG-36
View MARC record | catkey: 14755869