Irradiation growth in annealed Zircaloy-2
Description
Irradiation growth in annealed Zircaloy-2 has been studied at temperatures of 3530 K and 5530 K. Growth is initially rapid during irradiation at 3530 K but saturates above the dose of 2 x 1024 n/m2. The saturation growth strain is found to be strongly dependent upon crystallographic texture. At 5530 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 peak 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. (author)
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- ND-R--204(R)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 10494155
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ANNEALING; DIMENSIONS; HIGH TEMPERATURE; INTERSTITIALS; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; TEXTURE; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; CHROMIUM ADDITIONS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; HEAT TREATMENTS; IRON ADDITIONS; POINT DEFECTS; RADIATION EFFECTS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Also published in J. Nucl. Materials, 1979, v. 79(2) p. 302-311.