Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li2TiO3

Timur V. Kulsartov, Irina L. Tazhibayeva, Yuriy Gordienko, Yevgen Chikhray, Kunihiko Tsuchiya, Hiroshi Kawamura, A.V. Kulsartova

2011

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DOI 10.13182/fst11-a12616

Data confidence 70 medium

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Abstract

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.