Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation

Timur Kulsartov, Zhanna Zaurbekova, Irina Tazhibayeva, Yuriy Ponkratov, Vyacheslav Gnyrya, Gunta Kizane, Evgeny Nesterov, Natalia Varlamova

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This paper describes the experiments on study of tritium and helium generation and release processes from lead-lithium eutectics Li15.7Pb. The irradiation was performed at the IVG.1M research reactor at 6 MW of thermal power. The irradiation temperature increased step by step from 225 to 550 °C. A qualitative assessment of the experimental results showed that as the temperature rises above 390 °C, the tritium flux from the sample consisting of T 2 and HT molecules decreases. It was concluded that the observed effect is similar to the previously observed one for lead-lithium eutectics with Li17Pb83 composition.

Original languageEnglish
JournalFusion Engineering and Design
Publication statusPublished - 1 Jan 2019



  • Helium
  • Lead-Lithium eutectics
  • Neutron irradiation
  • Tritium

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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