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Control of tritium in FFHR-2 self-cooled Flibe blanket

Authors
Journal
Fusion Engineering and Design
0920-3796
Publisher
Elsevier
Publication Date
Volume
81
Identifiers
DOI: 10.1016/j.fusengdes.2005.09.017
Keywords
  • Flibe
  • Tritium
  • Blanket
  • Redox Control
  • Permeation
  • Beryllium

Abstract

Abstract The application of Flibe (2LiF + BeF 2 mixed molten salt) to a blanket material of force-free helical reactor (FFHR-2) was discussed based on our recent experiments on redox control of Flibe by Be and on hydrogen permeation through Flinak (0.465LiF + 0.115NaF + 0.42 KF mixed molten salt) as a fluid simulant of Flibe. The two experimental works were carried out under the collaboration work of JUPITER-II. To maintain Flibe in the blanket loop under reduction condition is a key issue to transform TF to T 2 with a fast reaction rate. In order to achieve that, proper rates of Be dissolution and reduction reaction of TF to T 2 in Flibe have to be established in the self-cooled blanket. The overall material balance of tritium in the FFHR-2 system was discussed in terms of the tritium permeation through Flibe and the tritium recovery rate.

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