Detailed Particle and Power Fluxes Into ITER Castellated Divertor Gaps During ELMs

Plasma deposition in narrow gaps between tiles of ITER plasma-facing components during ELMs is simulated by means of particle-in-cell technique. The particle and power loads onto and between the divertor tiles are estimated for a multispecies plasma. We simulate an equal mixture of deuterium and tritium (T) for the main plasma with one impurity, the carbon (C). The aim of this paper is to know whether the C ions can enter the narrow gaps between tiles and with which energy. Due to its radioactivity, the T deposition in the gaps is also of high interest and is estimated. The two basic orientations of the gap with respect to the magnetic field lines, poloidal and toroidal, have been studied. The global penetration of the two hydrogen species into the gap is on the order of the gap width ( ~ 0.5 mm), and their own contribution on the total heat flux to the gap is given. The main impurity penetrates into the gap in between 50% to 70% of the total plasma-deposition length but with a power deposited representing less than 1% of the total deposited power.