Tritium Extraction from Lithium-Lead in the EU DEMO Blanket Using Permeator Against Vacuum. (19th May 2017)

• Record Type: Journal Article
• Authors: D'Auria, V.; Dulla, S.; Ravetto, P.; Savoldi, L.; Utili, M.; Zanino, R.
• Is Part Of: Fusion science and technology. Volume 71:Number 4(2017)
• Page Start: 537
• Page End: 543
• Publication Date: 2017-05-19
• Subjects: DEMO breeding blanket -- lithium-lead -- Tritium Extraction System -- Permeator Against Vacuum; Fusion reactors -- Periodicals; Nuclear fusion -- Periodicals; Fusion reactors; Nuclear fusion; Periodicals; 621.48405
• DOI: 10.1080/15361055.2017.1291252
• Languages: English
• ISSNs: 1536-1055

Abstract

Abstract: The current studies on the development of the EU DEMO breeding blanket include among the options the use of liquid Lithium-Lead (17Li-83Pb) as tritium breeder (and multiplier), with different coolants. As the tritium is steadily produced in the blanket during the reactor operation, suitably efficient strategies for the Tritium Extraction System (TES) from the breeder must be developed, allowing a closed fuel cycle in situ and avoiding tritium accumulation in the machine. The Permeator Against Vacuum (PAV) appears to be one of the most promising solutions to achieve this goal. In this paper, the performance of a PAV system is studied by means of different models describing the transport of tritium in the liquid PbLi and in the metallic membrane separating it from the vacuum. The comparison of the results for different membrane materials and size of the device, for a given target efficiency, allows to optimize the PAV design, also taking into account corrosion issues. The approximations and limitations of the adopted models are also addressed.