Abstract
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°C and Zircaloy-2 up to 14.7 × 1025 n • m-2, approximately 24 dpa, in a boiling water reactor at approximately 300°C. Baseline transmission electron microscopy showed that the Zr3Fe secondary-phase particles in the binary system were larger and fewer in number than the Zr (Fe, Cr)2 and Zr2(Fe, Ni) particles in Zircaloy-2. An analysis of the irradiated binary alloy revealed only limited dissolution of Ze3Fe, suggesting little dispersion of iron into the matrix, while at the same time a higher 〈a〉-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 nanoclusters. A delay in the onset of 〈c〉-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 〈a〉 and 〈c〉 loops is described. The implication this may have on irradiation-induced growth of zirconium fuel cladding is also discussed.
| Original language | English |
|---|---|
| Title of host publication | Zirconium in the Nuclear Industry |
| Subtitle of host publication | 18th International Symposium |
| Editors | Robert J. Comstock, Arthur T. Motta |
| Publisher | ASTM International |
| Pages | 796-822 |
| Number of pages | 27 |
| ISBN (Electronic) | 9780803176416 |
| DOIs | |
| Publication status | Published - 2018 |
| Externally published | Yes |
| Event | International Symposium on Zirconium in the Nuclear Industry 2016 - Hilton Head, United States of America Duration: 15 May 2016 → 19 May 2016 Conference number: 18th https://www.astm.org/DIGITAL_LIBRARY/STP/SOURCE_PAGES/STP1597.htm |
Publication series
| Name | ASTM Special Technical Publication |
|---|---|
| Volume | STP 1597 |
| ISSN (Print) | 0066-0558 |
Conference
| Conference | International Symposium on Zirconium in the Nuclear Industry 2016 |
|---|---|
| Country/Territory | United States of America |
| City | Hilton Head |
| Period | 15/05/16 → 19/05/16 |
| Internet address |
Keywords
- BF-STEM
- BWR
- Dislocation analysis
- Iron
- Irradiation growth
- Precipitation
- Proton irradiation
- Zircaloy-2
- Zirconium
Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver