DIII-D latest results and implications

Conference · Tue Nov 01 04:00:00 EST 1988

OSTI ID:6583353

Callis, R; Luxon, J; Scoville, T; Simonen, T; Stambaugh, R

The DIII-D tokamak has demonstrated the feasibility of the divertor configuration for future reactor relevant devices. H-mode (good) confinement has been demonstrated for deuterium discharges in both single-null and double-null divertor configurations and under a variety of heating scenarios including neutral beam injection, electron cyclotron heating, and ohmic heating. Plasma beta values (..beta.. = 6.8%) near expected theoretical limits (3.5 I/aB) have been demonstrated. Plasma currents are limited by safety factors q > 2 near the surface of the plasma. Energy confinement improves with increasing plasma current until q decreases below 3. Divertor heat flow has been documented and initial boundary physics studies carried out. Non-inductive current drive has been demonstrated using neutral beam injection. 7 refs., 8 figs., 1 tab.

• Research Organization: General Atomics Co., San Diego, CA (USA)
• DOE Contract Number: AC03-84ER51044
• OSTI ID: 6583353
• Report Number(s): GA-A-19398; CONF-881031-47; ON: DE89004349
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101* -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
BEAM INJECTION HEATING
CLOSED PLASMA DEVICES
CONFINEMENT
CONFINEMENT TIME
DOUBLET-3 DEVICE
ECR HEATING
ELECTRIC HEATING
EQUILIBRIUM
HEATING
HIGH-FREQUENCY HEATING
JOULE HEATING
MHD EQUILIBRIUM
PLASMA CONFINEMENT
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES