Some oxide ceramics as reactor materials
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Date
1958-06-02
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Melbourne University Press on behalf of The Australian Atomic Energy Commission
Abstract
Although the conventional advantages of ceramics lie in their favourable high temperature properties reactor technology has not yet made use of these properties, mainly because of their uncertain behaviour under irradiation. The fabrication and properties of beryllia, uranium dioxide and thoria, and of mixed oxide systems, are discussed.
Description
Physical copies held by ANSTO Library at DDC: 539.7/348
Keywords
Oxides, Ceramics, Materials, Temperature range, Irradiation, Fabrication, Uranium dioxide, Graphite
Citation
Reeve, K. D. (1958). Some oxide ceramics as reactor materials. Paper present to the Australian Atomic Energy Symposium, 1958, "Peaceful Uses of Atomic Energy In Australia", Sydney, June 2 to 6, 1958. In Australian Atomic Energy Symposium, 1958 : proceedings of a Symposium on the Peaceful Uses of Atomic Energy in Australia held in Sydney from June 2 to 6, 1958. Carlton, Victoria : Melbourne University Press on behalf of the Australian Atomic Energy Commission, (pp. 161-167).