Candidte blanket concepts for a European fusion power plant study

摘要

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.