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

This article outlines Kyoto Fusioneering's (KF's) initial engineering and development activities for its self-cooled lithium lead-type blanket: Self-Cooled Yuryo Lithium-Lead Advanced (SCYLLA©). We provide details on overall design, including an initial tritium breeding ratio (TBR) assessm...

Full description

Saved in:
Bibliographic Details
Published in:IEEE transactions on plasma science 2022-11, Vol.50 (11), p.4406-4412
Main Authors: Pearson, R., Baus, C., Konishi, S., Mukai, K., D'Angio, A., Takeda, S.
Format: Article
Language:English
Subjects:
Adaptability
Blankets (fusion reactors)
Ceramic fiber reinforced ceramics
Composite materials
Fabrication
fusion power generation
fusion reactor design
Fusion reactors
Heat exchangers
Heat transfer
High temperature
high-temperature energy applications
Inductors
industrial engineering
Lead
Lithium
Neutrons
Production
R&D
Radiation effects
Reactors
Research & development
Scylla
Sieve plates
Silicon carbide
silicon carbide composite
Tritium
tritium breeding blanket
Citations: Items that this one cites
Items that cite this one
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:This article outlines Kyoto Fusioneering's (KF's) initial engineering and development activities for its self-cooled lithium lead-type blanket: Self-Cooled Yuryo Lithium-Lead Advanced (SCYLLA©). We provide details on overall design, including an initial tritium breeding ratio (TBR) assessment via neutronics analysis, as well as the status of SCYLLA©-relevant R&D. This includes silicon carbide composite (SiCf/SiC) manufacturing techniques, tritium extraction, materials compatibility, and heat transfer, which are being explored via collaboration with Kyoto University. Results of previous work in relation to this R&D are presented. Permeability coefficients indicate a promising property of SiCf/SiC tritium hermeticity at high temperatures. Tritium extraction technology via vacuum sieve tray (VST) is shown to be demonstrated at engineering scale. A local TBR of up to 1.4 can be achieved with the SCYLLA© configuration. Fabrication methods for various SiCf/SiC components including the blanket module, heat exchanger, and flow path components are provided. A tritium compatible high-temperature SiCf/SiC heat exchanger is discussed. Commercial viability and reactor adaptability are considered as a theme throughout. Finally, KF's plans to build a facility for demonstration reactor relevant testing of a SCYLLA© prototype in the mid-2020s, which will provide a significant step toward commercial fusion energy, are presented.
ISSN:0093-3813
1939-9375
DOI:10.1109/TPS.2022.3211410