Simulations of DIII-D divertor biasing with the LEDGE code

Conference · Tue Sep 01 04:00:00 EDT 1992

OSTI ID:6559844

Rensink, M E; Milovich, J; Rognlien, T

We use the LEDGE 2-d fluid model for the edge plasma to determine the effects of electrically biasing the outboard divertor plate in DIII-D. The LEDGE code includes classical perpendicular and parallel current flows as well as E x B and diamagnetic drifts. Boundary conditions at the divertor plates allow the sheath parameters to vary with current flow across the sheath. Ohmic heating and convective heat flow associated with the current flow are included. Neutrals originating at the divertor plates due to recycling are represented by a fluid model. We explore the effect of cross-field drifts and variations in the bias voltage. The current-voltage characteristic, inboard/outboard heat flux asymmetry and radial plasma profiles are computed. We show that cross-field drifts have a strong effect on the plasma profiles at the diverter plates. Differential biasing of the inboard and outboard divertor plates can significantly modify the naturally occurring outboard/inboard heat flux asymmetry, but only weakly affects radial profiles at the outboard plate.

• Research Organization: Lawrence Livermore National Lab., CA (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6559844
• Report Number(s): UCRL-JC-110-843; CONF-9209181--7; ON: DE93010500
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
BOUNDARY LAYERS
CLOSED PLASMA DEVICES
COMPUTER CODES
COMPUTERIZED SIMULATION
DIVERTORS
DOUBLET-3 DEVICE
ELECTRIC POTENTIAL
FLOW MODELS
HEAT FLUX
L CODES
LAYERS
MATHEMATICAL MODELS
PLASMA SCRAPE-OFF LAYER
SIMULATION
THERMONUCLEAR DEVICES
TOKAMAK DEVICES