Advanced divertor experiments on DIII-D

Conference · Mon Apr 01 04:00:00 EST 1991

OSTI ID:5905512

Schaffer, M J; Mahdavi, M A; Osborne, T; Petrie, T W; Stambaugh, R D ^[1]; Buchenauer, D ^[2]; Hill, D N ^[3]; Klepper, C C ^[4]

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1. General Atomics, San Diego, CA (USA)
2. Sandia National Labs., Livermore, CA (USA)
3. Lawrence Livermore National Lab., CA (USA)
4. Oak Ridge National Lab., TN (USA)

The poloidal divertor is presently favored for next-step, high-power tokamaks. The DIII-D Advanced Divertor Program (ADP) aims to gain increased control over the divertor plasma and tokamak boundary conditions. This paper reports experiments done in the first phase of the ADP. The DIII-D lower divertor was modified by the addition of a toroidally symmetric, graphite-armoured, water-cooled divertor-biasing ring electrode at the entrance to a gas plenum. The plenum will eventually contain a He cryogenic loop for active divertor pumping. The separatrix strike'' position is controlled by the lower poloidal field shaping coils and can be varied smoothly from the ring electrode upper surface to the divertor floor far from the entrance aperture. External power, at up to 550 V and 8 kA separately, has been applied to the electrode to date. 5 refs., 5 figs.

• Research Organization: General Atomics, San Diego, CA (USA)
• Sponsoring Organization: DOE; USDOE, Washington, DC (USA)
• DOE Contract Number: AC03-89ER51114; AC05-84OR21400; AC04-76DP00789; W-7405-ENG-48
• OSTI ID: 5905512
• Report Number(s): GA-A-20480; CONF-910609--10; ON: DE91011138
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
BOUNDARY LAYERS
CARBON
CONFINEMENT
DIVERTORS
DOUBLET REACTORS
ELEMENTAL MINERALS
ELEMENTS
GRAPHITE
H-MODE PLASMA CONFINEMENT
HEAT FLUX
LAYERS
MINERALS
NONMETALS
PLASMA CONFINEMENT
PLASMA SCRAPE-OFF LAYER
POLOIDAL FIELD DIVERTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS