Critical behavior of interfacial t-ZrO2 and other oxide features of zirconium alloy reaching critical transition condition
Source abstract
Abstract
Abstract Transition of zirconium alloys during uniform corrosion is not expected but inevitable, since it accelerates the degradation of corrosion property. Up to now, proposed transition mechanisms have not clearly illustrated the critical behavior of interfacial t-ZrO2 and other oxide features under the critical transition condition. Therefore, study on the under-transition sample was carried out. Microscopically, the monoclinic stress increases after transition, strongly supporting the occurrence of transformation from t-ZrO2 to m-ZrO2. A sudden stress decrease in t-ZrO2 occurs in pre-transition region of the under-transition sample. This decrease might be attributed to formation of permeable paths which induce consumption of interfacial oxygen vacancies. This critical behavior possibly destabilizes the grown t-ZrO2 grains. And the post-transition regions will propagate after t-ZrO2 transformation. The transition region in the oxide consists of lateral cracks propagated transgranularly and large numbers of interconnected pores, both of which may originate from t-ZrO2 transformation. Current works suggest that three critical behaviors of t-ZrO2 induce oxide fracture and corrosion transition. The growth nature and evolution mechanism of t-ZrO2 are further illustrated. Even though t-ZrO2 layer similarly evolve as the ZrO suboxide layer, the unstable nature of t-ZrO2 indicates that it is severely affected by grain size, stress value and chemical composition.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (35)
Show source-provided references
1. Corrosion of zirconium alloys10.1016/B978-0-08-056033-5.00063-X ↗
2. Corrosion of zirconium alloys in nuclear power plants
3. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
4. Towards a mechanistic understanding of corrosion mechanisms in zirconium alloys
5. Residual stresses and tetragonal phase fraction characterization of corrosion tested Zircaloy-4 using energy dispersive synchrotron X-ray diffraction10.1016/j.jnucmat.2012.07.025 ↗
6. Corrosion of new zirconium claddings in 500 °C/10.3 MPa steam: effects of alloying and metallography
7. Property degradation of tetragonal zirconia induced by low-temperature defect reaction with water molecules10.1021/cm040167h ↗
8. Study of sub-oxide phases at the metal-oxide interface in oxidized pure zirconium and Zr-1.0% Nb alloy by using SEM/FIB/EBSD and EDS techniques10.1016/j.jnucmat.2016.04.038 ↗
9. Tetragonal phase stability in ZrO film formed on zirconium alloys and its effects on corrosion resistance10.1016/j.actamat.2006.10.030 ↗
10. Residual stresses in high temperature corrosion of pure zirconium using elasto-viscoplastic model: application to the deflection test in monofacial oxidation10.1016/j.apsusc.2015.08.225 ↗
11. In-situ stress analysis of the Zr/ZrO2 system as studied by Raman spectroscopy and deflection test in monofacial oxidation techniques10.1016/j.apsusc.2016.05.074 ↗
12. Research on the existence and stability of interfacial tetragonal zirconia formed on zirconium alloys10.1016/j.jnucmat.2019.151846 ↗
13. Effect of grain size on mechanical properties of submicrometer 3Y-TZP: fracture strength and hydrothermal degradation10.1111/j.1551-2916.2007.01643.x ↗
14. Hydrothermal aging behavior of nanocrystalline Y-TZP ceramics10.1111/j.1551-2916.2010.04341.x ↗
15. The correlation between tetragonal phase and the undulated metal/oxide interface in the oxide films of zirconium alloys10.1016/j.jnucmat.2019.06.039 ↗
16. Utilising DualEELS to probe the nanoscale mechanisms of the corrosion of Zircaloy-4 in 350 °C pressurised water10.1016/j.jnucmat.2015.06.022 ↗
17. Focussed ion beam sectioning for the 3D characterisation of cracking in oxide scales formed on commercial ZIRLO™ alloys during corrosion in high temperature pressurised water10.1016/j.corsci.2011.08.013 ↗
18. On the evolution of wave structure at the oxide/metal interface during oxidation of Zr alloys10.1016/j.corsci.2014.07.002 ↗
19. A study into the impact of interface roughness development on mechanical degradation of oxides formed on zirconium alloys10.1016/j.jnucmat.2015.01.028 ↗
20. A Raman study of the nanocrystallite size effect on the pressure–temperature phase diagram of zirconia grown by zirconium-based alloys oxidation10.1016/S0022-3115(01)00756-5 ↗
21. Review of stress fields in zirconium alloys corrosion scales10.1016/j.corsci.2015.03.004 ↗
22. Potentialities of Raman imaging for the analysis of oxide scales formed on Zircaloy-4 and M5® in air at high temperature10.1007/s11085-012-9331-5 ↗
23. Modelling of the mechanical behavior of the metal–oxide system during Zr alloy oxidation10.1016/S0022-3115(98)00045-2 ↗
24. New insight into crack formation during corrosion of zirconium-based metal-oxide systems10.1016/j.actamat.2013.04.009 ↗
25. Critical assessment of finite element analysis applied to metaleoxide interface roughness in oxidising zirconium alloys10.1016/j.jnucmat.2015.05.002 ↗
26. Finite element analysis of the tetragonal to monoclinic phase transformation during oxidation of zirconium alloys10.1016/j.jnucmat.2014.08.020 ↗
27. Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO oxide10.1016/j.jnucmat.2014.09.073 ↗
28. Identifying suboxide grains at the metal-oxide interface of a corroded Zr-1.0%Nb alloy using (S)TEM, transmission-EBSD and EELS10.1016/j.micron.2014.10.004 ↗
29. The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr-Sn-Nb alloys10.1016/j.actamat.2013.03.046 ↗
30. Atom probe tomography study of alloying element distributions in Zr alloys and their oxides10.1016/j.jnucmat.2013.08.055 ↗
31. The microstructure and microtexture of zirconium oxide films studied by transmission electron backscatter diffraction and automated crystal orientation mapping with transmission electron microscopy10.1016/j.actamat.2014.07.062 ↗
32. Mechanism of the α-Zr to hexagonal-ZrO transformation and its impact on the corrosion performance of nuclear Zr Alloys10.1016/j.actamat.2019.08.051 ↗
33. The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys10.1016/j.corsci.2015.07.003 ↗
34. On the oxidation behavior of (Zr,Nb)2Fe under simulated nuclear reactor conditions10.1016/j.corsci.2016.08.006 ↗
35. The role of alloying elements in the initiation of nanoscale porosity in oxide films formed on zirconium alloys10.1016/j.corsci.2013.08.006 ↗