Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant

This paper describes the work performed for the power plant conceptual studies (PPCS) reactor model AB, a ‘near-term’ fusion power reactor based on limited extrapolations from today knowledge on technology and plasma physic assumption, featuring a helium-cooled lithium lead (HCLL) blanket concept and a He cooled divertor.The main design rational and characteristics of the PPCS model AB as well as the main assumption and achieved results are reported. The reactor is able to supply to the grid a net electrical power of 1.5 GWe for a fusion power of 4.2 GWth and features a major radius of 9.56 m. A tritium breeding ratio (TBR) of 1.13 will assure the tritium self sufficiency.