Neutron irradiation growth of Zirconium alloys. Final report for the period 01 September 1994 - 14 August 1996
- 1. China Inst. of Atomic Energy, Beijing (China)
Description
Samples of Zircaloy-4 tubing and Zr-2.5wt%Nb sheet were thoroughly characterized with respect to their microstructures and crystallographic textures prior to irradiation. Following careful determination of their dimensions, the samples were irradiated in a neutron flux of 7 x 1012 n/m2.s (E > 1.0 MeV) at 340 ± 10 deg. C to various fluences. After irradiation, growth strains were measured and a study of the recovery of irradiation growth by annealing was carried out. Only transient growth and part of the linear secondary growth regimes were investigated. Differences in growth behaviour of different Zircaloy-4 materials was attributed to differences in grain structures and slight differences in composition. In Zr-2.5wt%Nb growth strain at a given fluence increased with the original amount of cold work. In Zircaloy-4 the irradiation growth strain was recoverable (>90%) by post-irradiation annealing at 600 deg. C. (author). 11 refs, 18 figs, 3 tabs
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Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- IAEA-R--8073-F
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28024872
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ANNEALING; EXPERIMENTAL DATA; GRAIN GROWTH; IRRADIATION; MICROSTRUCTURE; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; ZIRCALOY 4
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAT TREATMENTS; INFORMATION; IRON ADDITIONS; MATERIALS; NUMERICAL DATA; RADIATION EFFECTS; RADIATION FLUX; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS