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Publisher Summary This chapter discusses the investigation of water cooled lithium–lead blankets jointly performed by CEA and the JRC of ISPRA in the framework of the European DEMO blanket study program. The reactor characteristics considered in the study were the following: DEMO-1 with double null plasma, neutron wall loading, outboard breeding blanket thickness, inboard breeding blanket thickness, no breeding elements behind diverters, unprotected first wall, and martensitic steel as structural material. Both inboard and outboard blankets were formed by 48 segment boxes made of water cooled steel structures that integrated the first wall and confined the breeding modules. These breeding modules consisted of cylindrical containers, whose axes were adapted to the toroidal D-shaped geometry; they are straight in the inboard region and curved in the outboard region. Each module contained lithium–lead and was cooled by a water tubes bundle. A continuous flowing of lithium–lead was imposed by tritium extraction outside the blanket. |
