Status of Fusion Reactor Blanket Evaluation Studies in France
Fusion Science and Technology / Volume 8 / Number 1P2A / July 1985 / Pages 491-500
Blanket and First-Wall Engineering / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40089
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In the frame of recent CEA studies aiming at the evaluation and at the comparison of various candidate blanket concepts in moderate power conditions (Pn∼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.
