Recent experimental results of the rates of hydrogen permeation through metallic materials in the presence of liquid Pb17Li alloy: influence on the performance and design of tritium recovery equipment
The eutectic Pb-17Li is considered a potential candidate as a breeding material for thermonuclear machines because of its favourable characteristics; the lead present in the eutectic is, in fact, a good neutron multiplier for obtaining a high tritium breeding ratio. Moreover, the eutectic itself has good thermal and physicochemical properties and has low corrosion rates on the structural material of the blanket containers at the operating temperature. Recent data on the H(2) or D(2) solubility in the eutectic are so low that a higher tritium pressure is created even with a low tritium inventory in the blanket. Consequently, tritium permeation from the eutectic to the cooling water system and to the environment is very probable. Since the overall tritium permeation rate, with no barriers, can be controlled by the tritium mass transfer step between the eutectic and the structural material, experimental work is being carried out in order to determine the kinetics of hydrogen mass transfer through metallic walls wetted by the eutectic. The experimental results show that the permeation rate is much lower than that so far considered in the feasibility study.
Bibliographic Reference: Article: Fusion Engineering and Design, Vol. 8 (1989), pp. 365-370
Record Number: 199010334 / Last updated on: 1994-12-01
Original language: en
Available languages: en