Simulation of Power and Particle Flows in the NSTX Edge Plasma
We simulate edge plasmas in NSTX double-null divertor configurations with the UEDGE two-dimensional fluid code. The carbon impurity density in the core plasma and total radiated power increase with the core heating power and the magnitude of the physical and chemical sputtering in the divertor. Up/down plasma asymmetries are generated by classical cross-field particle drifts. With the standard toroidal magnetic field direction (ion {del}B drift toward the lower x-point) the highest density occurs at the lower inboard divertor plate and the highest heat flux at the upper outboard divertor plate. Simulations of 3-d edge plasma turbulence with the BOUT code show that anomalous radial transport at the outboard midplane should be similar in magnitude for NSTX and DIII-D.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE Office of Defense Programs (DP) (US)
- DOE Contract Number:
- W-7405-Eng-48
- OSTI ID:
- 794013
- Report Number(s):
- UCRL-JC-136705-REV-1; TRN: US0300664
- Resource Relation:
- Journal Volume: 290-293; Conference: 14th International Conference on Plasma Surface Interactions, Rosenheim (DE), 05/22/2000--05/26/2000; Other Information: PBD: 18 May 2000
- Country of Publication:
- United States
- Language:
- English
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Two-dimensional electric fields and drifts near the magnetic separatrix in divertor tokamaks
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