Progress in Studies of Li₁₇Pb₈₃ as Liquid Breeder for Fusion Reactor Blankets

A review of the experimental and conceptual design work in progress at JRC-Ispra to investigate the feasibility of the eutectic Li₁₇Pb₈₃ as a liquid breeder for experimental power reactors is presented. Results of recent measurements to implement the data base of this material are given in the following areas: physical parameters, hydrogen solubility and recovery, chemical reactivity with air and water, compatibility with steel. The studies carried out on blanket concepts for the INTOR (International Tokamak Reactor)/NET (Next European Torus) projects are outlined and discussed.