CERAMIC BREEDER MATERIAL DEVELOPMENT

Citation
N. Roux et al., CERAMIC BREEDER MATERIAL DEVELOPMENT, Fusion engineering and design, 41, 1998, pp. 31-38
Citations number
33
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
09203796
Volume
41
Year of publication
1998
Pages
31 - 38
Database
ISI
SICI code
0920-3796(1998)41:<31:CBMD>2.0.ZU;2-H
Abstract
Lithium-based ceramics have long been recognized as promising tritium- breeding materials for fusion reactor blankets. In particular, their h igh thermal stability and chemical inertness are favorable safety char acteristics. The most important qualification for a candidate ceramic breeder material is most likely, the ability to withstand the rigors o f long-term irradiation at high temperature and under large temperatur e gradients. As a group, the lithium-based ceramics have shown good ir radiation behaviour and excellent tritium release characteristics. Ind ividual materials performance will depend upon the actual application, namely, pebble bed versus pellet concept, higher versus lower cooling temperature, etc. Recently Li2ZrO3 and Li2TiO3 were selected as the b reeder material for the ITER breeding blanket due to their excellent t ritium release behaviour at low temperature. Issues being addressed in support of current blanket design studies will be highlighted. (C) 19 98 Elsevier Science S.A. All rights reserved.