V.A. Soukhanovskii, J.-W. Ahn, R.E. Bell, D.A. Gates, S. Gerhardt, R. Kaita, E. Kolemen, B.P. LeBlanc, R. Maingi, M. Makowski, R. Maqueda, A.G. McLean, J.E. Menard, D. Mueller, S.F. Paul, R. Raman, A.L. Roquemore, D.D. Ryutov, S.A. Sabbagh, H.A. Scott
||Nuclear Fusion, 2011, Vol.51 (1), pp.012001 (4pp)
||Institute of Physics Journal
Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.