[en] In experimental fusion energy devices such as tokamaks, pump limiters are used to define the plasma edge as well as control the plasma density and impurity. Since these devices must operate at the edge of the plasma, they are subject to high heat flux incidence from the plasma side. In this paper, one of the active heat removal schemes considered for the outboard pump limiter of Tore Supra, a tokamak under construction in Cadarache, France, is analyzed in some detail. The scheme involves cooling by forced convective nucleate boiling of water at the limiter leading edges and by forced convection of high pressure helium at its front face. 14 refs., 5 figs., 4 tabs