Experimental and Modeling Study of the Divertor Heat Flux Width on EAST (PhD Oral-24)

A comprehensive study of the divertor heat flux width is carried out on the experimental advanced superconducting tokamak (EAST). Experimentally, factors like plasma current, heating scheme and plasma operating regime are found to have significant effects on the divertor heat flux width on EAST. Edge plasma fluid codes BOUT$++$ and SOLPS are employed to simulate the EAST discharges to figure out the potential reasons to the effects of these factors on the divertor heat flux width on EAST. Detailed results and analysis will be presented in the “PhD Oral-24” section.