Author/Authors :
Groth، نويسنده , , M. and Owen، نويسنده , , L.W. and Porter، نويسنده , , G.D. and Brooks، نويسنده , , N.H. and Fenstermacher، نويسنده , , M.E. and Meyer، نويسنده , , W.H. and Leonard، نويسنده , , A.W. and Petrie، نويسنده , , T.W. and Rudakov، نويسنده , , D.L. and Wang، نويسنده , , G. and Watkins، نويسنده , , J.G. and Wolf، نويسنده , , N.S.، نويسنده ,
Abstract :
Measurements and modeling of the 2D poloidal Dα intensity distribution in DIII-D low density L-mode and medium density ELMy H-mode plasmas indicate that the core plasma is predominately fueled near the divertor X-point region. The neutral deuterium and ion carbon emission were measured in the divertor and inner main chamber scrape-off layer (SOL) using a plasma imaging technique, covering 85% of the poloidal cross-section. Typically, the peak emission in the inner main SOL at the tokamak midplane was three orders of magnitude lower than in the divertor. For discharges with the ion B × ∇B drift direction toward the lower divertor the UEDGE/DEGAS codes predict strong core plasma fueling from the significantly higher density and lower temperature plasma calculated in the inner divertor leg. The concomitant carbon ion flow reversal in the inner divertor leg enhances the leakage of carbon from the divertor into the main SOL, and hence into the core.
Keywords :
Poloidal drifts , plasma imaging , DIII-D , Carbon transport , Fueling