Experimental studies of divertor stabilization in an axisymmetric tandem mirror

A divertor coil set has been installed on the Tara tandem mirror [Nucl. Fusion 2 2, 549 (1982); P l a s m a P h y s i c s a n d C o n t r o l l e d N u c l e a r F u s i o n R e s e a r c h 1 9 8 4 (IAEA, Vienna, 1985), Vol. 2, p. 285] for stabilization of m=1 flutelike modes. The effectiveness of d...

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Bibliographic Details
Published in:The Physics of fluids (1958) 1988-07, Vol.31 (7), p.2009-2016
Main Authors: Casey, J. A., Lane, B. G., Irby, J. H., Brau, K. L., Golovato, S. N., Guss, W. C., Kesner, J., Post, R. S., Sevillano, E., Zielinski, J.
Format: Article
Language:English
Subjects:
Exact sciences and technology
Magnetic confinement and equilibrium
Physics
Physics of gases, plasmas and electric discharges
Physics of plasmas and electric discharges
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Summary:A divertor coil set has been installed on the Tara tandem mirror [Nucl. Fusion 2 2, 549 (1982); P l a s m a P h y s i c s a n d C o n t r o l l e d N u c l e a r F u s i o n R e s e a r c h 1 9 8 4 (IAEA, Vienna, 1985), Vol. 2, p. 285] for stabilization of m=1 flutelike modes. The effectiveness of divertor stabilization is discussed in experiments where m=1 modes are driven to instability by plug electron cyclotron heating (ECH) in an ion cyclotron heated (ICH) plasma. The instability onset is characterized by thresholds in ECH power, fueling rate, ICH power, and mapping radius of the divertor null. In general, the stability is enhanced by mapping the null radially inwards into the plasma. The interdependence of these parameters and their effect on equilibrium profiles and stability boundaries are discussed.
ISSN:0031-9171
2163-4998
DOI:10.1063/1.866649