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

P. Blynskiy, Ye Chikhray, T. Kulsartov, M. Gabdullin, Zh Zaurbekova, G. Kizane, Ye Kenzhin, A. Tolenova, E. Nesterov, A. Shaimerdenov

Research output: Contribution to journalArticlepeer-review

Abstract

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.

Original languageEnglish
Pages (from-to)9186-9192
Number of pages7
JournalInternational Journal of Hydrogen Energy
Volume46
Issue number13
DOIs
Publication statusPublished - 19 Feb 2021

Keywords

  • Fusion reactor
  • Lithium ceramics
  • Neutron irradiation
  • Tritium

ASJC Scopus subject areas

  • Renewable Energy, Sustainability and the Environment
  • Fuel Technology
  • Condensed Matter Physics
  • Energy Engineering and Power Technology

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