Published November 1991 | Version v1
Journal article

Out-of-pile tritium extraction from lithium orthosilicate-based ceramics

  • 1. Groupe de Chimie du Solide, Lab. de Physique de la Matiere Condensee, Ecole Polytechnique, 91 - Palaiseau (France)
  • 2. CEA/CEREM, 91 - Gif-sur-Yvette (France)

Description

Ceramics based on the lithium orthosilicate (Li4SiO4) are candidates as blanket materials for forthcoming fusion reactors. Lithium ceramics, with controlled stoichiometry and microstructure, have been prepared by sol-gel route and sintering at 650-800deg C. The enhancement of the lithium conductivity is realized either by introducing mobile ion vacancies in the lithium sites of the orthosilicate type structure, or by formation of a composite material containing a few wt% of LiOH. Tritium extraction experiments, from out-of-pile, show no relation between the tritium release and the lithium bulk-diffusion within the grains. At low temperature, the tritium release is governed by water chemistry and can be described by OH-/OT- recombination and desorption. At high temperature, the tritium release is probably governed by surface reaction between adsorbed H2 and surface OT-. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
185
Journal Issue
1
Series
J. Nucl. Mater.
Journal Page Range
19-28
ISSN
0022-3115
CODEN
JNUMA