Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system

Fumito Okino, Pattrick Calderoni, Ryuta Kasada, Satoshi Konishi

Research output: Contribution to journalArticlepeer-review

13 Citations (Scopus)


This paper describes the quantitative analysis for the design of a tritium extraction system that uses liquid PbLi droplets in vacuum (Vacuum Sieve Tray, VST), for application to the ITER helium-cooled lithium lead (HCLL) test blanket system (TBS). The parametric dependences of tritium extraction efficiency from the main geometrical features such as initial droplet velocity, nozzle head height, nozzle diameter, and flow rate are discussed. With nozzle diameters between 0.4 and 0.6 mm, extraction efficiency is estimated from 0.77 to 0.96 at the falling height of 0.5 m, with flow rate between 0.2 and 1.0 kg/s. The device has a height of 1.6 m, within the external dimensions of the HCLL Test Blanket Module (TBM), and no additional pumping power is required. The attained results are considered attractive not only for ITER, but also in view of the application of the VST concept as a candidate tritium extraction system for the European Union's demonstration fusion reactor (DEMO). The extraction efficiency of a single droplet column, which is the basis of the design analysis presented, has been validated experimentally with hydrogen. However, further experiments are required on an integrated system with size relevant to the proposed HCLL-TBS design to validate system-level effects, particularly regarding the desorption process in an array of multiple droplets.

Original languageEnglish
Pages (from-to)1748-1753
Number of pages6
JournalFusion Engineering and Design
Issue numberPart B
Publication statusPublished - 2016


  • DEMO relevancy
  • Droplet
  • HCLL
  • PbLi
  • Tritium extraction


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