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Research on eutectic Pb-17Li is part of the blanket studies carried out in the frame of the EC Fusion Technology Programme. Two blanket concepts using liquid Pb-17Li as breeder, one water-cooled and the other self-cooled, are being investigated and are among the candidates for testing in the Next Step machines. After briefly reviewing the main features of both concepts, the paper presents the progress on the Pb-17Li database acquisition, namely: - thermophysical properties; - solubility of metallic and non metallic elements (with a special attention to tritium); - chemical reactivity; - corrosion of structural materials and related mechanical effects, and - tritium production and recovery.

Additional information

Authors: CASINI G, JRC Ispra (IT);SANNIER J, CEA, IRDI/DCAEA/SCECF, Fontenay-aux-Roses (FR)
Bibliographic Reference: Article: Journal of Nuclear Materials, Vol. 179-181 (1991) pp. 47-52
Record Number: 199111168 / Last updated on: 1994-12-02
Original language: en
Available languages: en