Experiments on tritium generation and yield from lithium ceramics during neutron irradiation

Blynskiy P. Chikhray Y. Kulsartov T. Gabdullin M. Zaurbekova Z. Kizane G. Kenzhin Y. Tolenova A. Nesterov E. Shaimerdenov A.
19 February 2021 Elsevier Ltd

International Journal of Hydrogen Energy
2021 #46 Issue 13 9186 - 9192 pp.

The vacuum extraction method with a mass spectrometry registration of tritium is presented in paper. It can provide a full-range analysis of gas phase composition in the chamber with samples under neutron irradiation. Lithium ceramics Li₂TiO₃ in the form of pebbles with lithium enrichment on ⁶Li isotope of 96% was examined. The paper shows the results of reactor experiments on study the extraction of tritium-containing molecules from lithium ceramics Li₂TiO₃ at various temperatures and reactor power levels at the WWR-K research reactor (Almaty, Kazakhstan). The time dependences of tritium yield from the ampoule with ceramics during reactor irradiation were obtained. Near-surface concentrations of tritium and hydrogen atoms on the ceramics surface under reactor irradiation were estimated.

Fusion reactor , Lithium ceramics , Neutron irradiation , Tritium

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Al-Farabi Kazakh National University, 71, Al-Farabi Ave., Almaty, 050040, Kazakhstan
Kazakh-British Technical University, 59 Tole Bi Str., Almaty, 050000, Kazakhstan
Institute of Chemical Physics, University of Latvia, Raiņa Bulvāris 19, Centra Rajons, Rīga, LV-1586, Latvia
Institute of Nuclear Physics, 1 Ibragimova Str., Almaty, 050032, Kazakhstan
National Research Tomsk Polytechnic University, Tomsk Polytechnic University, Lenina Av., 30, Tomsk, 634050, Russian Federation
Satbayev University, 22, Satbayev Str., Almaty, 050013, Kazakhstan

Al-Farabi Kazakh National University
Kazakh-British Technical University
Institute of Chemical Physics
Institute of Nuclear Physics
National Research Tomsk Polytechnic University
Satbayev University

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