Experimental studies of divertor stabilization in an axisymmetric tandem mirror

Journal Article · Fri Jul 01 00:00:00 EDT 1988 · Phys. Fluids; (United States)

DOI:https://doi.org/10.1063/1.866649· OSTI ID:7231345

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; others, and

A divertor coil set has been installed on the Tara tandem mirror (Nucl. Fusion 22, 549 (1982); Plasma Physics and Controlled Nuclear Fusion Research 1984 (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.

• Research Organization: Plasma Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139
• OSTI ID: 7231345
• Journal Information: Phys. Fluids; (United States), Journal Name: Phys. Fluids; (United States) Vol. 31:7; ISSN PFLDA
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700107* -- Fusion Energy-- Plasma Research-- Instabilities
DIVERTORS
ECR HEATING
EQUILIBRIUM
FLUTE INSTABILITY
HEATING
HIGH-FREQUENCY HEATING
ICR HEATING
INSTABILITY
MAGNETIC MIRRORS
MAPPING
OPEN PLASMA DEVICES
PLASMA
PLASMA HEATING
PLASMA INSTABILITY
PLASMA MACROINSTABILITIES
STABILIZATION
TANDEM MIRRORS
THERMONUCLEAR DEVICES