Status of Fusion Reactor Blanket Evaluation Studies in France

In the frame of recent CEA studies aiming at the evaluation and at the comparison of various candidate blanket concepts in moderate power conditions (P_n∼2 MW/m²), the present work examines the neutronic and thermomechanical performances of a water cooled Li₁₇Pb₈₃ tubular blanket and those of a helium cooled canister blanket taking advantage of the excellent breeding capability of composite Beryllium / LiAlO₂ (85/15%) breeder elements. The purpose of the following discussion is to justify the impetus for these reference concepts and to summarize the state of their evaluation studies updated by the continuous assimilation of calculations and experiments in progress.