Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system
作者： Fumito Okino , Pattrick Calderoni , Ryuta Kasada , Satoshi Konishi
DOI: 10.1016/J.FUSENGDES.2015.10.004
关键词:
摘要: Abstract This paper describes the quantitative analysis for design of a tritium extraction system that uses liquid PbLi droplets in vacuum (Vacuum Sieve Tray, VST), application to ITER helium-cooled lithium lead (HCLL) test blanket (TBS). The parametric dependences efficiency from main geometrical features such as initial droplet velocity, nozzle head height, diameter, and flow rate are discussed. With diameters between 0.4 0.6 mm, is estimated 0.77 0.96 at falling height 0.5 m, with 0.2 1.0 kg/s. device has 1.6 m, within external dimensions HCLL Test Blanket Module (TBM), no additional pumping power required. attained results considered attractive not only ITER, but also view VST concept candidate European Union's demonstration fusion reactor (DEMO). single column, which basis presented, been validated experimentally hydrogen. However, further experiments required on an integrated size relevant proposed HCLL-TBS validate system-level effects, particularly regarding desorption process array multiple droplets.
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