Irradiation growth in annealed Zircaloy-2
Description
Irradiation growth in annealed Zircaloy-2 has been studied at 353 K and 553 K. Growth is initially rapid during irradiation at 353 K but saturates above a dose of 2 X 1024 n/m2. The saturation growth strain is found to be strongly dependent upon crystallographic texture. At 553 K, growth in longitudinal specimens attenuates with dose but does not saturate up to a dose of 12.3 X 1024 n/m2; in transverse specimens growth is observed to saturate at a dose of less than 1.3 X 1024 n/m2. The effect of changing irradiation temperature has been studied. The observed growth behaviour is interpreted in terms of a growth model in which growth is produced by the formation of sub-microscopic interstitial clusters on prism planes, possibly combined with a small volume increase. (Auth.)
Additional details
Publishing Information
- Journal Title
- J. Nucl. Mater.
- Journal Volume
- 79
- Journal Issue
- 2
- Series
- J. Nucl. Mater.
- Journal Page Range
- 302-311
- ISSN
- 0022-3115
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10469444
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- DIMENSIONS; FAST NEUTRONS; HIGH TEMPERATURE; INTERSTITIALS; MEDIUM TEMPERATURE; PHYSICAL RADIATION EFFECTS; PRESSURE TUBES; RADIATION DOSES; TEMPERATURE DEPENDENCE; TEXTURE; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; BARYONS; CHROMIUM ADDITIONS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; FERMIONS; HADRONS; IRON ADDITIONS; NEUTRONS; NUCLEONS; POINT DEFECTS; RADIATION EFFECTS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS