Community Research and Development Information Service - CORDIS


The inventory of tritium in fusion reactor blankets and the permeation of tritium into the blanket coolant or out of the blanket can be calculated by a numerical code. In a liquid breeder blanket, the input data of this code are solubility and diffusivity of the liquid breeder material, and solubility, diffusivity, surface recombination rate, trapping properties and heat of transport (Soret effect) of the blanket structure material. In this review, the properties of Pb-17Li necessary for tritium transport calculations in blankets are studied, namely tritium solubility and diffusivity, and measurements are reported and compared with those of other authors.

Additional information

Authors: REITER F, JRC Ispra (IT)
Bibliographic Reference: Article: Fusion Engineering and Design, Vol. 14 (1991) pp. 207-211
Record Number: 199211074 / Last updated on: 1994-11-29
Original language: en
Available languages: en