Status and near-term plans for DIII-D

Conference · Thu Oct 01 04:00:00 EDT 1987

OSTI ID:6717694

Davis, L G; Callis, R W; Luxon, J L; Stambaugh, R D

The DIII-D tokamak at GA Technologies began plasma operation in February of 1986 and is dedicated to the study of highly non-circular plasmas. High beta operation with enhanced energy confinement is paramount among the goals of the DIII-D research program. Commissioning of the device and facility has verified the design capability including coil and vessel loading, volt-second consumption, bakeout temperature, vessel armor, and neutral beamline thermal integrity and control systems performance. Initial experimental results demonstrate the DIII-D is capable of attaining high confinement (H-mode) discharges in a divertor configuration using modest neutral beam heating or ECH. Record values of I/sub p/aB/sub T/ have been achieved with ohmic heating as a first step toward operation at high values of toroidal beta and record values of beta have been achieved using neutral beam heating. This paper summarizes results to date and gives the near term plans for the facility. 13 refs., 6 figs., 1 tab.

• Research Organization: General Atomics Co., San Diego, CA (USA)
• DOE Contract Number: AC03-84ER51044
• OSTI ID: 6717694
• Report Number(s): GA-A-18997; CONF-871007-113; ON: DE89001807
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101 -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
700200* -- Fusion Energy-- Fusion Power Plant Technology
BEAM INJECTION HEATING
CLOSED PLASMA DEVICES
CONFINEMENT
CONTAINERS
CONTROL SYSTEMS
DOUBLET-3 DEVICE
ECR HEATING
ENERGY SYSTEMS
EXPERIMENT PLANNING
HEATING
HIGH-FREQUENCY HEATING
ICR HEATING
LIMITERS
PLANNING
PLASMA CONFINEMENT
PLASMA HEATING
POWER SYSTEMS
PRESSURE VESSELS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES