Experiment on recovery of hydrogen from fluidized Li17Pb83 blanket

Taiki Muneoka, S. Fukada, R. Yoshimura, K. Katayama, Y. Edao, T. Hayashi

Research output: Chapter in Book/Report/Conference proceedingChapter

3 Citations (Scopus)


Development of an efficient tritium recovery method is indispensable in order to compose a liquid blanket system of a D-T fusion reactor in the near future. Here, tritium recovery using a bubbling tower is focused on, and the behavior of H transfer between fluidized lithium-lead (Li-Pb) and gas bubbles of Ar-H2 or pure Ar is examined analytically and experimentally under isothermal conditions. Gas of Ar-H2 or pure Ar is injected into fluidized Li-Pb through an I-shape nozzle made from SS-316. Time variations of the H2 concentration in gas bubbles that come out from fluidized Li-Pb are measured by gas chromatography. Mass-transfer coefficients to correlate rates of H atom transfer between Li-Pb and gas bubbles are obtained by fitting analytical equations to experimental results. The solution is derived under conditions where H transfer between bubbles and liquid Li-Pb is limited by diffusion in the Li-Pb boundary layer. The parameters such as bubble diameter and terminal rising velocity which are used in order to derive analytic formula are estimated from balance among several forces such as gravity, surface tension, inertia force and so on. The behavior of hydrogen transfer at gas-liquid interfaces in liquid blanket is investigated in terms of the mass-transfer coefficient obtained under various conditions.

Original languageEnglish
Title of host publicationFusion Science and Technology
PublisherAmerican Nuclear Society
Number of pages5
ISBN (Electronic)9781510811836
Publication statusPublished - Sept 1 2015

All Science Journal Classification (ASJC) codes

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


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