[3B10-12] Fusion Reactor System, Design, Application 2

3:35 PM - 3:50 PM JST(6:35 AM - 6:50 AM UTC)

[3B11] Study on tritium breeding performance of various liquid metal breeders for laser inertial fusion reactors

*KANTA UTSUMI¹, Kaoru Omiya¹, Masatoshi Kondo¹ (1. Tokyo Tech)

Keywords:

Laser inertial fusion,TBR,Liquid breeder blanket,Lithium lead alloy,Lithium gallium alloy,Lithium indium alloy

The resource of tritium is limited in the world, which is the fuel of fusion reactors. Laser inertial fusion reactors are suitable for tritium breeding because they have sufficient blanket volume for tritium production. In the present study, tritium breeding performance of various liquid lithium alloys was studied by means of neutron transport calculation with PHITS code, which revealed lower melting point and/or excellent fuel breeding performance. Low-melting point liquid lithium alloys (e.g., gallium-lithium alloys and indium-lithium alloys) do not show sufficient fuel breeding performance. The fuel breeding performance of liquid lithium-lead alloys at eutectic composition (i.e., 16 mol% lithium) has been studied. Tritium breeding performance can be promoted at higher lithium concentration, although the liquidus temperature becomes higher.