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The main elements defining the tungsten content of an ITER plasma, i.e. the gross erosion, the prompt redeposition and the transport in the H-mode edge transport barrier are reviewed and it is investigated, whether the low tungsten concentration limit in the core calls for additional control of the divertor parameters or the ELM energy beyond the requirements set by the power handling capability of the divertor. The outcome is rather positive, since no further control seems to be required mainly because of the favourable transport in the H-mode edge transport barrier which provokes hollow tungsten profiles in the edge transport barrier for the expected pedestal parameters. Keywords: First wall, Tungsten, Erosion, ELM, Cross field transport, ITER