Fusion Testing Device

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Date

1988-04

Authors

Carrera, R.
Driga, M. D
Gully, J. H
Hsieh, K. T
Montalvo, E
Ordonez, C
Rosenbluth, M
Walls, W. A
Weldon, W. F
Woodson, H. H.

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Abstract

A recently proposed fusion testing device called IGNITEX is described in this paper. The original idea was recently proposed by M.N. Rosenbluth, W.A. Weldon, and H.H. Woodson. The bases for the concept are B. Coppi's ideas for a compact thermonuclear experiment and technological progress in high-current pulsed-power systems. The concept utilizes a single-turn-coil tokamak to produce a 20 Tesla magnetic field and induce plasma currents in excess of 12 Megamperes which beat the plasma ohmically to thermonuclear temperatures. The IGNITEX experiment can produce a self-sustained fusion reaction and a stable ignited phase of the plasma discharge. Low-cost unconventional fusion technologies based on single-turn coils and homopolar generators will be employed. Low-voltage operation will minimize problems of insulation degradation and increase the strength of the magnet system. The neutron wall load during ignition will be high enough to be relevant to the design of future fusion systems. Machine activation problems will be addressed with a close shielding of the device. Diagnostic equipment will be located outside of the primary shielding, in a large experimental hall. A simple tritium system will provide the fuel to the device. Remote maintenance and repair of in-vessel components will be utilized. The compactness, the simplicity of design and the unconventional magnet and power supply technologies of IGNITEX make the basic cost or construction of the experiment relatively low.

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R. Carrera, M. D. Driga, J. H. Gully, K. T. Hsieh, E. Montalvo, C. Ordonez, M. Rosenbluth, W. A. Walls, W. F. Weldon, H. H. Woodson, “Fusion testing device,” Proceedings, International Symposium on Fusion Nuclear Technology, Tokyo, Japan, April 1988.