Community Research and Development Information Service - CORDIS

Abstract

This report presents a data collection of tritium-material interaction parameters in fusion reactor materials. The parameters are: diffusivity, solubility, heat of transport and surface recombination rate of tritium, trap concentration and energy difference between trap and solution sites. These data are needed as input data in numerical codes for the calculation of tritium recycling from the first wall or plasma facing surfaces, of tritium inventory in the first wall, and of tritium permeation through the first wall. Since tritium leakage by permeation through fusion reactor structures is a critical phenomenon when considering the overall efficiency of the fuel-cycle, the report also surveys methods of reducing tritium loss by permeation barriers. These barriers are layers of relatively low tritium permeability either applied to the surface of a material or formed by surface oxidation. The effectiveness of permeation barriers consisting of a wide range of materials is considered and a comparison made taking into account not only the permeation reduction obtained but also the suitability of the coating in practical and engineering terms.

Additional information

Authors: REITER F, JRC Ispra (IT);FORCEY K S, JRC Ispra (IT);GERVASINI G, JRC Ispra (IT)
Bibliographic Reference: EUR 15217 EN (1993) 54 pp., free of charge
Availability: Available from Joint Research Centre, Publication Department, I-21020 Ispra (Va.) (IT)
Record Number: 199511572 / Last updated on: 1995-12-12
Category: PUBLICATION
Original language: en
Available languages: en