In-vessel component designs for a self-cooled lithium-lead fusion reactor

This paper describes an advanced fusion power reactor based on advanced plasma physics assumptions and large technological extrapolation compared with present-day knowledge. In-vessel components are based on the use of SiCf/SiC composite's structure and the use of high-temperature Pb-17Li both as coolant and breeder for the blanket. The use of high-temperature super-conducting coils is also expected. A net electrical output of 1500 MWe is assumed. Tritium breeding self-sufficiency and acceptable operating parameters have been obtained. The resulting conceptual power plant has the potential for a thermal efficiency as high as 61% and for reaching good safety standard. The technological extrapolations assumed in this study provide an indication of the necessary R&D for addressing the most critical issues. (C) 2003 Elsevier Science B.V. All rights reserved.