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Tritium production and extraction in blankets using lithium, the eutectic alloy Pb-17Li, the molten salt Li(2)BeF(4) (Flibe) or aqueous lithium salt solutions as a liquid breeder material are studied in this paper. The physical properties of these materials which are important for tritium production, extraction and material interaction are compiled and discussed. These are melting temperature, lithium density, tritium solubility and diffusivity, density, thermal conductivity, viscosity, specific heat and electric resistivity. The paper describes three liquid breeder blanket concepts developed for NET, a further concept using Flibe as a liquid breeder, and permeation through the vanadium first wall as the main tritium refuelling method. The three NET blanket concepts are the NET driver blanket using an aqueous Li salt solution and a water-cooled and a self-cooled DEMO relevant blanket concept, both using Pb-17Li as a liquid breeder material. Due to the very large differences of tritium solubility in the four liquid breeder materials studied, different methods or conditions are necessary for tritium extraction from the blanket in each case. Finally, calculations of tritium inventory, permeation and recycling in the water-cooled NET Pb-17Li blanket and in a self-cooled blanket, using Pb-17Li or Flibe as a liquid breeder material and V as a first wall material, are presented and discussed.

Additional information

Authors: REITER F, JRC Ispra (IT)
Bibliographic Reference: Paper presented: Course and Workshop on Tritium Technology, Varenna (IT), June 6-15, 1989
Availability: Available from (1) as Paper EN 34926 ORA
Record Number: 199011519 / Last updated on: 1994-12-02
Original language: en
Available languages: en
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