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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: 15th International Symposium
By
Bruce Kammenzind
Bruce Kammenzind
1
Bettis Laboratory
,
West Mifflin, PA,
USA
, Symposium Chairman and STP Editor
Search for other works by this author on:
Magnus Limbäck
Magnus Limbäck
editor
2
Westinghouse Electric Sweden
,
Västerås,
Sweden
,
Editorial Chairman and STP Editor
Search for other works by this author on:
ISBN-10:
0-8031-4514-4
ISBN:
978-0-8031-4514-6
No. of Pages:
136
Publisher:
ASTM International
Publication date:
2009

This paper briefly reviews work by the author identifying and describing in-reactor deformation mechanisms of materials and structures used in nuclear reactors, in particular, Zircaloy-2, Zircaloy-4, and Zr-2.5Nb, and the CANDU fuel channel (comprising Zr alloy pressure tubes, calandria tubes, and spacers). The discussion is set in the context of contemporary findings of other workers in the international community. The following themes are highlighted: The contributions of creep and growth to deformation; c-component dislocations and the fluence dependence of irradiation growth; anisotropy of irradiation growth; deformation equations and pressure tube-to-calandria tube contact in CANDU reactors; low temperature flux (damage rate) dependence of deformation rates. The first developments were reported in 1976 at the third conference in this series and there are ongoing developments in all areas. The linear low temperature flux dependence of creep and growth rates is yet to be satisfactorily explained.

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