DIII-D latest results and implications
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6244444
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.
- Research Organization:
- General Atomics, San Diego, CA (US)
- OSTI ID:
- 6244444
- Report Number(s):
- CONF-881031-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 15:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
700206 -- Fusion Power Plant Technology-- Environmental Aspects
700208 -- Fusion Power Plant Technology-- Inertial Confinement Technology
BEAM INJECTION
BETA RATIO
CONFIGURATION
CONFINEMENT
CURRENT-DRIVE HEATING
DATA
DEUTERIUM
DIVERTORS
ECR HEATING
ELECTRIC HEATING
FEASIBILITY STUDIES
HEAT FLOW
HEATING
HIGH-FREQUENCY HEATING
HYDROGEN ISOTOPES
INERTIAL CONFINEMENT
INFORMATION
ISOTOPES
JOULE HEATING
LIGHT NUCLEI
NEUTRAL ATOM BEAM INJECTION
NUCLEI
NUMERICAL DATA
ODD-ODD NUCLEI
PHYSICS
PLASMA
PLASMA CONFINEMENT
PLASMA DRIFT
PLASMA HEATING
RESISTANCE HEATING
SAFETY
STABLE ISOTOPES
THEORETICAL DATA
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
700206 -- Fusion Power Plant Technology-- Environmental Aspects
700208 -- Fusion Power Plant Technology-- Inertial Confinement Technology
BEAM INJECTION
BETA RATIO
CONFIGURATION
CONFINEMENT
CURRENT-DRIVE HEATING
DATA
DEUTERIUM
DIVERTORS
ECR HEATING
ELECTRIC HEATING
FEASIBILITY STUDIES
HEAT FLOW
HEATING
HIGH-FREQUENCY HEATING
HYDROGEN ISOTOPES
INERTIAL CONFINEMENT
INFORMATION
ISOTOPES
JOULE HEATING
LIGHT NUCLEI
NEUTRAL ATOM BEAM INJECTION
NUCLEI
NUMERICAL DATA
ODD-ODD NUCLEI
PHYSICS
PLASMA
PLASMA CONFINEMENT
PLASMA DRIFT
PLASMA HEATING
RESISTANCE HEATING
SAFETY
STABLE ISOTOPES
THEORETICAL DATA
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS