Conceptual Design of Advanced Blanket Using Liquid LiPb

Author

Hasegawa, T. ; Yamamoto, Y. ; Konishi, S.

Author_Institution

KyotoUniv., Kyoto

fYear

2007

fDate

17-21 June 2007

Firstpage

1

Lastpage

4

Abstract

This paper describes a conceptual design of an advanced blanket using liquid lithium lead (Li₁₇Pb₈₃) metal and high temperature material. Liquid lithium lead metal is expected as a material to solve some problems of solid blankets and expected to be operated at high temperature above900 degree C. We examined a feasible structure using advanced materials (the SiC/SiC compostite, reduced activation ferritic steel(RAFS)) tritium permeability, tritium breeding ratio and heat transfer behavior at high temperature above 600 C. We have obtained a TBR 1.25 with a limited thickness, and investigated the effect of neutron multiplier Be. The TBR greater than 1.4 was obtained with reasonable neutron flux and heat distribution.

Keywords

fusion reactor blankets; fusion reactor design; heat transfer; lithium compounds; neutron flux; silicon compounds; steel; tritium handling; advanced blanket; heat distribution; heat transfer; high temperature material; liquid lithium lead metal; neutron flux; neutron multiplier; reduced activation ferritic steel; solid blankets; tritium breeding ratio; tritium permeability; Building materials; Cooling; Heat transfer; Helium; Inorganic materials; Lead; Lithium; Neutrons; Plasma temperature; Silicon carbide; Be; LiPb; TBR; liquid breeder;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on

Conference_Location

Albuquerque, NM

Print_ISBN

978-1-4244-1193-1

Electronic_ISBN

978-1-4244-1194-8

Type

conf

DOI

10.1109/FUSION.2007.4337881

Filename

4337881