Abstract
The breeding blanket is an essential in-vessel component for fusion power plants based on the deuterium–tritium fuel. It is submitted to severe operating conditions such as high surface heat flux on the first wall (>0.5 MW/m 2) and to very high 14 MeV neutron flux (>10 18 n/m 2 s). Because of the simultaneous requirement of very demanding performances, such as tritium breeding self-sufficiency, high thermal cycle efficiency, high availability and high safety standards, the number of candidate breeding blanket concepts is limited. After recalling advantages and drawbacks of possible combinations of structural materials, coolants, and breeder materials, this paper summarizes the characteristics and the performances of some potential candidate concepts for a European power plant study and associated required R&D.
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