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Simulation of Main-Chamber Recycling in DIII-D with the UEDGE Code

Conference ·
This report demonstrates a computer simulation model for single-null diverted plasma configurations that include simultaneous interaction of the scrape-off layer (SOL) plasma with toroidally symmetric main-chamber limiter surfaces and divertor plate surfaces. The simulations use the UEDGE code which treats the SOL plasma and recycled neutrals as two-dimensional toroidally symmetric fluids. The spatial domain can include field lines that intersect main chamber surfaces in the far scrape-off layer, which allows the model to include simultaneous plasma contact with both divertor and main chamber targets. Steady-state simulation results for low-density L-mode plasma discharges in DIII-D show that total core fueling increases by about 70 percent when the separatrix-baffle gap is reduced from 6 cm to 3 cm. The additional core fueling is due to neutrals which originate from the ion particle flux incident on the upper outer divertor baffle.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA
Sponsoring Organization:
USDOE
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
891056
Report Number(s):
UCRL-PROC-220897
Country of Publication:
United States
Language:
English

References (5)

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Neutral Gas Transport Modeling with DEGAS 2 journal January 1994
A new look at density limits in tokamaks journal December 1988
The magnitude of plasma flux to the main-wall in the DIII-D tokamak journal September 2005