The removal of Helium in future fusion devices with significant alpha particle production is essential. The removal of the "ash" has to be effcient enough to provide a "clean" core plasma and to prevent from high throughput of the fuelling gas in the pumping system. We concentrate in this paper on the transport in the plasma edge, i.e. scrape-off layer and divertor. For an overview of the work on this topic done so far, the reader is referred to and references therein. The exhaust studies in reversed B aimed on the understanding of the Helium and Deuterium edge transport towards the divertor by comparing the reversed and the forward B configuration.