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
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