DIII-D research program progress

Conference · Thu Nov 01 04:00:00 EST 1990

OSTI ID:6311576

Stambaugh, R D

A summary of highlights of the research on the DIII-D tokamak in the last two years is given. At low q, toroidal beta ({beta}{sub T}) has reached 11%. At high q, {epsilon}{beta}{sub p} has reached 1.8. DIII-D data extending from one regime to the other show the beta limit is at least {beta}{sub T}(%) {ge} 3.5 I/aB (MA, m, T). Prospects for using H-mode in future devices have been enhanced. The discovery of negative edge electric fields and associated turbulence suppression have become part of an emerging theory of H-mode. Long pulse (10 second) H-mode with impurity control has been demonstrated. Radial sweeping of the divertor strike points and gas puffing under the X-point have lowered peak divertor plate heat fluxes a factor of 3 and 2 respectively. T{sub i} = 17 keV has been reached in a hot ion H-mode. Electron cyclotron current drive (ECCD) has produced up to 70 kA of driven current. Program elements now beginning are fast wave current drive (FWCD) and an advanced divertor program (ADP). 38 refs., 10 figs.

• Research Organization: General Atomics, San Diego, CA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC03-89ER51114
• OSTI ID: 6311576
• Report Number(s): GA-A-20273; CONF-901025--39; IAEA-CN--53/A-1-4; ON: DE91006409
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101* -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
CONFINEMENT
DIVERTORS
DOUBLET REACTORS
ELECTRIC FIELDS
ELECTRON DENSITY
H-MODE PLASMA CONFINEMENT
IMPURITIES
NON-INDUCTIVE CURRENT DRIVE
PLASMA CONFINEMENT
PLASMA IMPURITIES
RESEARCH PROGRAMS
TEMPERATURE DISTRIBUTION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS