Published July 1988 | Version v1
Journal article

Ceramic breeder materials

  • 1. Argonne National Lab. (USA)
  • 2. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)
  • 3. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

Description

Ceramic materials are under investigation as potential breeder material in fusion reactors. This paper will review candidate materials with respect to (a) fabrication routes and characterization, (b) properties in as-fabricated and irradiated condition, and (c) experimental results from laboratory and in-pile investigations on tritium transport and release. Also discussed are the resources of beryllium, which is being considered as a neutron multiplier. The comparison of ceramic properties that is attempted here aims at the identification of the most-promising material for use in a tritium breeding blanket. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
155-157
Journal Issue
pt.A
Series
J. Nucl. Mater.
Journal Page Range
188-201
ISSN
0022-3115
CODEN
JNUMA

Conference

Title
3. international conference on fusion reactor materials (ICFRM-3).
Dates
4-8 Oct 1987.
Place
Karlsruhe (Germany, F.R.).