The effect of iron on dislocation evolution in model and commercial zirconium alloys - 2016-0068
- University of Manchester, School of Materials, Materials Performance Centre, Manchester, M13 9PL. (United Kingdom)
- Chalmers University of Technology, Dept. of Applied Physics, SE-412 96 Goteborg (Sweden)
- Studsvik Nuclear AB, SE-611 82 Nykoping, (Sweden)
- Westinghouse Electric Company, Columbia, SC (United States)
- Rolls-Royce, Derby, DE21 7XX (United Kingdom)
- National Nuclear Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG (United Kingdom)
- Westinghouse Electric Sweden AB, SE-721 63 Vasteras (Sweden)
Although the evolution of irradiation-induced dislocation loops has been well correlated with irradiation-induced growth phenomena, the effect of alloying elements on this evolution remains elusive, especially at low fluences. To develop a more mechanistic understanding of the role iron has on loop formation, we used state-of-the-art techniques to study a proton-irradiated Zr-0.1Fe alloy and proton- and neutron-irradiated Zircaloy-2. The two alloys were irradiated with 2-MeV protons up to 7 dpa at 350 deg. C and Zircaloy-2 up to 14.7 X 10{sup 25} n. m{sup -2}, approximately 24 dpa, in a boiling water reactor at approximately 300 deg. C. Baseline transmission electron microscopy showed that the Zr{sub 3}Fe secondary-phase particles in the binary system were larger and fewer in number than the Zr(Fe,Cr){sub 2} and Zr{sub 2}(Fe,Ni) particles in Zircaloy-2. An analysis of the irradiated binary alloy revealed only limited dissolution of Ze{sub 3}Fe, suggesting little dispersion of iron into the matrix, while at the same time a higher -loop density was observed compared with Zircaloy-2 at equivalent proton dose levels. We also found that the redistribution of iron during irradiation led to the formation of iron nano-clusters. A delay in the onset of -loop nucleation in proton-irradiated Zircaloy-2 compared with the binary alloy was observed. The effect of iron redistributed from secondary-phase particles because of dissolution on the density and morphology of and loops is described. The implication this may have on irradiation-induced growth of zirconium fuel cladding is also discussed. (authors)
- Research Organization:
- ASTM International, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, PA, 19428-2959 (United States)
- OSTI ID:
- 22788424
- Resource Relation:
- Conference: 18. International Symposium on Zirconium in the Nuclear Industry, Hilton Head, SC (United States), 15-19 May 2016; Other Information: Country of input: France; 63 refs.
- Country of Publication:
- United States
- Language:
- English
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