The E×B drift due to an applied radial electric field in a tokamak with poloidal divertor can speed the flow of plasma out of the scrape‐off region, and provide a means of externally controlling the flow rate and thus the width of the density fall‐off. An experiment in the Wisconsin levitated toroidal octupole, using E×B drifts alone, demonstrates divertor‐like behavior, including 70% reduction of plasma density near the wall and 40% reduction of plasma flux to the wall, with no adverse effects on confinement of the main plasma.