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Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li2TiO3

T. Kulsartov, I. Tazhibayeva, Yu. Gordienko, E. Chikhray, K. Tsuchiya, H. Kawamura, A. Kulsartova

Fusion Science and Technology / Volume 60 / Number 3 / Pages 1139-1142

October 2011

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Lithium-based oxide ceramics are considered as the candidate materials for solid breeders of future fusion reactors' blankets. Breeder's goal is effective, safe and reliable production of tritium as a result of lithium-neutron reactions. Main candidates as a breeder material are Li2O, Li4SiO4, Li2TiO3 and Li2ZrO3, which are able to keep their physical-chemical properties despite of lithium burn-up. Lithium metatitanate Li2TiO3 attracts the great attention due to its chemical stability and high speed of tritium release under low temperatures (from 200 to 400°C). This paper contains the results of the studies on tritium and helium release from the samples of irradiated lithium ceramics Li2TiO3.

 
 
 
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