Detailed heat loads into ITER castellated divertor gaps uring ELMs

We have performed kinetic calculations of plasma deposition in narrow gaps between tiles of ITER plasma facing components during ELMs. We simulate an equal mixture of deuterium and tritium for the main plasma and one impurity, carbon. The aim of this study is to know whether the carbon can enter the narrow gaps between tiles and with which energy. Due to its radioactivity, the tritium deposition is also of high interest. The two basic orientations of the gap with respect to the magnetic field, poloidal and toroidal, have been studied. The global penetration of the two hydrogen species into the gap is in the order of the gap width (~0.5 mm) and their own contribution on the total heat flux to the gap is estimated. The main impurity penetrates into the gap in between 50 to 70% of the total plasma deposition in the gap but with a power deposited representing less than 1% of the total deposited power.