The prospect of liquid metal (LM) employment in fusion tokamak reactors blankets has been discussed. Special attention is being paid to MHD problems connected with LM pumping in a strong magnetic field, and to the design technique. The possibility of realizing such pumping is considered for the hybrid blanket of the Soviet experimental fusion reactor. The most important parameters in the conceptual design of such a blanket are-low value of MHD flow resistance in ducts parallel to the magnetic field; the possibility of insulating film development, separating the coolant from the hydraulic duct walls, anomalous heat transfer in the magnetic field, etc. Application of LM for plasma impurity control components and first wall protection using a LM surface are also analysed. An experiment with a droplet diaphragm in a tokamak-type installation is described. The results are presented as to the changes in reactor characteristics due to LM application.