European Water-Cooled Lithium-Lead Blanket Designs for a Demo Reactor

Ph. Labbe; L. Giancarli; L. Baraer; P. Leroy; J. Mercier; Y. Severi; J. Quintric-Bossy

doi:dx.doi.org/10.13182/FST91-A29474

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European Water-Cooled Lithium-Lead Blanket Designs for a Demo Reactor

Ph. Labbe, L. Giancarli, L. Baraer, P. Leroy, J. Mercier, Y. Severi, J. Quintric-Bossy

Fusion Science and Technology / Volume 19 / Number 3P2A / May 1991 / Pages 1006-1011

Blanket Technology / dx.doi.org/10.13182/FST91-A29474

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Within the framework of the European DEMO blanket study programme, CEA and the JRC of ISPRA develop a water cooled lithium-lead blanket concept. Considering the low breeding coverage ratio of the DEMO-1 reactor configuration currently specified in the E-C programme, the use of beryllium was envisaged in order to reach the tritium self-sufficiency which corresponds to an equivalent tridimensional Tritium Breeding Ratio (TBR) above 1.05. This beryllium is either directly immersed in the liquid metal (Pb-17Li) or completely separated from it.