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 an...

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Bibliographic Details
Published in:Fusion engineering and design 2006-02, Vol.81 (1), p.469-476
Main Authors: Li Puma, A., Berton, J.L., Brañas, B., Bühler, L., Doncel, J., Fischer, U., Farabolini, W., Giancarli, L., Maisonnier, D., Pereslavtsev, P., Raboin, S., Salavy, J.-F., Sardain, P., Szczepanski, J., Ward, D.
Format: Article
Language:English
Subjects:
Applied sciences
Controled nuclear fusion plants
Efficiency
Energy
Energy. Thermal use of fuels
Exact sciences and technology
HCLL blanket
Installations for energy generation and conversion: thermal and electrical energy
Integration
Power plant
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Summary: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 GW e for a fusion power of 4.2 GW th and features a major radius of 9.56 m. A tritium breeding ratio (TBR) of 1.13 will assure the tritium self sufficiency.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2005.08.041