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Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium

2013; Elsevier BV; Volume: 442; Issue: 1-3 Linguagem: Inglês

10.1016/j.jnucmat.2013.03.036

1873-4820

Timur Kulsartov, Yuriy Gordienko, I. Tazhibayeva, E.A. Kenzhin, Nikolay Barsukov, A.O. Sadvakasova, A.V. Kulsartova, Zhanna Zaurbekova,

Muon and positron interactions and applications

The results of tritium and helium gas release from lithium ceramics samples Li2TiO3 irradiated at the WWR-K reactor (Almaty, Kazakhstan) and from beryllium samples irradiated at the BN-350 reactor (Aktau, Kazakhstan) and the IVG.1M reactor (Kurchatov, Kazakhstan) are presented. Experimentally obtained thermal desorption (TDS) spectra have shown that the dependence of tritium release from lithium ceramics has a complicated behavior and to a large extent depends on lithium ceramics type. Nevertheless, it was found that the total amount of tritium released from all types of lithium ceramics has the same order of magnitude, equal to about 1011 Bq/kg. It was found that in the temperature range from 523 K to 1373 K the process of tritium release from lithium ceramics involves volume diffusion and thermoactivated tritium release from the accumulation centers generated under irradiation. TDS of beryllium samples enables us to obtain characteristics of tritium and helium release during linear heating, to determine integrated quantities of generated helium and tritium, and to determine parameters of release processes.