Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

UWFDM-1256 A Lithium Self-Cooled Blanket Concept for the HAPL Conceptual Inertial Confinement Reactor

Neutronics Analysis of A Self-Cooled Blanket for A Laser Fusion Plant with Magnetic Diversion

A blanket concept made of the low electrical conductivity SiCf/SiC composite and utilizing Li17Pb83 as coolant and tritium breeder has been developed and integrated with the magnetic diversion system. Neutronics issues related to tritium breeding adequacy particularly with the area lost to the dump plates at the ring and point cusps were addressed. Radiation damage and lifetime considerations f...

ELECTRICALLY INSULATING COATINGS FOR V - Li SELF - COOLED BLANKET IN A FUSION SYSTEM

The blanket system is one of the most important components in a fusion reactor because it has a major impact on both the economics and safety of fusion energy. The primary functions of the blanket in a deuterium/tritium-fueled fusion reactor are to convert the fusion energy into sensible heat and to breed tritium for the fuel cycle. The liquid-metal blanket concept requires an electrically insu...

SiC/SiC Composite for an Advanced Fusion Power Plant Blanket

This paper describes the results of an exploratory study of blanket concepts based on SiC/SiC structure and LiPb breeder. An assessment of the performance of these concepts for advanced power plant application i s presented, key issues are identified, and constraints relating to the SiC/SiC properties are discussed.

UWFDM-1311 Neutronics Analysis of a Self-Cooled Blanket for a Laser Fusion Plant with Magnetic Diversion

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