Divertor heat load study in COMPASS using IR thermography and divertor probes.
P. (Petr) Vondráček, J. (Jiří) Adámek, J. (Jordan) Cavalier, A. Devitre et autres
Heat flux magnitude and distribution over first wall and plasma facing components is a key issue for next step fusion devices in order to avoid damage of inner vessel components and secure reliable operation. Radial profiles of parallel heat\nflux in present tokamaks …