Developing Models for the DIII-D Boundary Plasma

Abstract

Abstract. Development of the comprehensive codes used to study the boundary region of the DIII-D tokamak has been done in parallel with improvement of the diagnostics of this important region of the plasma. These codes have been used to interpret the diagnostic data and assist in design of improved divertor configurations. The development of codes used for analysis on DIII-D is described briefly. Model validation by comparing with the extensive DIII-D boundary region diagnostic data is also discussed.

Summary of the ARIES Town Meeting: ‘Edge Plasma Physics and Plasma Material Interactions in the Fusion Power Plant Regime’

“…The basic UEDGE models described have been used extensively to model edge plasma characteristics and wall fluxes for a number of existing tokamaks, e.g. DIII-D [51], NSTX [52], Alcator C-Mod [53] and JT60-U [54] as well as ITER [47] and some ARIES designs [44].…”