Published March 1998 | Version v1
Journal article

Fabrication development of Li2O pebbles by wet process

  • 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
  • 2. Nuclear Fuel Industries Ltd., Tokai-mura, Naka-gun, Ibaraki 319-11 (Japan)

Description

Lithium oxide (Li2O) is one of the best tritium breeding materials. A small sphere of Li2O is proposed in some designs of fusion blankets. Recently, reprocessing technology on irradiated ceramic tritium breeders was developed from the viewpoint of effective use of resources and reduction of radioactive wastes. The wet process is advantageous for fabricating small Li2O pebbles from the reprocessed lithium-bearing solutions. Preliminary fabrication tests of Li2O pebbles by the wet process were carried out. However, the density of the pebbles obtained was only 55%. Therefore, process improvement tests were performed in order to increase the density of Li2O pebbles fabricated by this method. The improved process yielded Li2O pebbles in the target range of 80-85% T.D. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
253
Journal Page Range
p. 196-202
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
5. international symposium on fabrication and properties of ceramics for fusion energy and other high radiation environment as part of the 99. annual meeting of the American Ceramics Society
Dates
5-7 May 1997
Place
Cincinnati, OH (United States)

Optional Information

Notes
14 refs.