Title of article :
Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant
Author/Authors :
Li Puma، نويسنده , , A. and Berton، نويسنده , , J.L. and Braٌas، نويسنده , , B. and Bühler، نويسنده , , L. and Doncel، نويسنده , , J. and Fischer، نويسنده , , U. and Farabolini، نويسنده , , W. and Giancarli، نويسنده , , L. and Maisonnier، نويسنده , , D. and Pereslavtsev، نويسنده , , P. and Raboin، نويسنده , , S. and Salavy، نويسنده , , J.-F. and Sardain، نويسنده , , P. and Szczepanski، نويسنده , , J. and Ward، نويسنده , , D.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2006
Pages :
8
From page :
469
To page :
476
Abstract :
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. in 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.
Keywords :
Power plant , Integration , efficiency , HCLL blanket
Journal title :
Fusion Engineering and Design
Serial Year :
2006
Journal title :
Fusion Engineering and Design
Record number :
2352757
Link To Document :
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