journal article·2017-07

In-situ oxidation and short-time corrosion investigation on strain and dislocation during the generation and growth of ZrO 2

Zhen Wang, Bang-xin Zhou, Bing Chen, Wei Zhu, Bang Wen, Lu Wu, Hong-kui Tang, Zhong-qiang Fang, Qiang Li, Mei-yi Yao

Corrosion Science· Volume 122
Publisher page

Abstract

Abstract An In-situ oxidation test and a short time exposure corrosion test of Zircaloy-4 were carried out. A lot of dislocations generated in the nucleation and growth process of ZrO 2 are observed. Dislocations will be firstly distributed at the interface of ZrO 2 . With the growth of m-ZrO 2 grains, the number of dislocations at the interface increases. When the grain size of ZrO 2 reaches a critical value, the dislocations in the grains of ZrO 2 begin to appear. A compressive strain between semi-coherent planes of oxides was detected in a range from −0.3% to −6%.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Electronic and Structural Properties of Oxides · Advanced ceramic materials synthesis

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (26)

Show source-provided references
1. The role of lithium and boron on the corrosion of zircaloy-4 under demanding PWR-type conditions
2. Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe10.1016/S0022-3115(96)00453-9 ↗
3. High temperature steam oxidation study on Zr–2.5%Nb pressure tube under simulated LOCA condition10.1016/j.jnucmat.2012.09.027 ↗
4. Investigation of oxide layers formed on Zircaloy-4 coarse-grained specimens oxidised at 360°C in lithiated aqueous solution10.1016/j.corsci.2014.12.012 ↗
5. Identifying suboxide grains at the metal-oxide interface of a oxidised Zr-1.0%Nb alloy using(S) TEM, transmission-EBSD and EELS10.1016/j.micron.2014.10.004 ↗
6. Study of anisotropic behaviour for zirconium alloys corroded in lithiated water
7. Atom probe tomography study of alloying element distributions in Zr alloys and their oxides10.1016/j.jnucmat.2013.08.055 ↗
8. Analysis of oxidation behavior of the β-Nb phase formed in Zr-1. 5Nb alloy by using the HVEM
9. An investigation of the oxidation behaviour of zirconium alloys using isotopic tracers and high resolution SIMS10.1016/j.jnucmat.2013.07.053 ↗
10. New insight into crack formation during corrosion of zirconium-based metal-oxide systems10.1016/j.actamat.2013.04.009 ↗
11. Residual stresses and tetragonal phase fraction characterisation of corrosion tested Zircaloy-4 using energy dispersive synchrotron X-ray diffraction10.1016/j.jnucmat.2012.07.025 ↗
12. Effects of alloyed Si on the autoclave corrosion performance and periodic corrosion kinetics in Zr–Sn–Nb–Fe–O alloys10.1016/j.corsci.2015.08.043 ↗
13. Utilising DualEELS to probe the nanoscale mechanisms of the corrosion of Zircaloy-4 in 350°C pressurised water10.1016/j.jnucmat.2015.06.022 ↗
14. Crystal structure of the ZrO phase at zirconium/zirconium oxide interfaces10.1002/adem.201400133 ↗
15. How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys10.1016/j.actamat.2012.09.021 ↗
16. 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 ↗
17. Microstructural characterization of ZrO2 layers formed during the transition to breakaway oxidation10.1016/j.jnucmat.2010.01.021 ↗
18. Quantitative measurement of displacement and strain fields in the ZrO2 layer during the transition to nodular oxidation10.1016/j.corsci.2012.11.017 ↗
19. The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr–Sn–Nb alloys10.1016/j.actamat.2013.03.046 ↗
20. Oxidation characteristics of basal (0002) plane and prism (11–20) plane in HCP Zr10.1016/S0022-3115(02)01226-6 ↗
21. Study of the initial stage and anisotropic of oxide layer formed on Zircaloy-4
22. The initial oxidation of Zircaloy-4 in lithiated water under autoclave conditions as examined by TEM10.1016/j.corsci.2016.01.011 ↗
23. Second phase particles and their corrosion behavior of Zr-0.72Sn-0.32Fe-0.15Cr-0.97Nb alloy
24. TEM study on the initial oxidation of Zircaloy-4 thin foil specimens heated in a low vacuum air condition at 280–300°C10.1016/j.jnucmat.2017.02.019 ↗
25. An AES study of oxidation of polycrystalline zirconium at room temperature and low oxygen pressures10.1002/sia.740100402 ↗
26. Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-410.1016/j.corsci.2013.05.007 ↗