journal article·2021-01

Analysis of blister-like morphology on the oxide film of Zr-1Nb alloy corroded in lithiated water

Meiyi Yao, Jiao Huang, Keke Hou, Hanpei Zhao, Xue Liang, Jinlong Zhang, Bangxin Zhou, Qiang Li

Corrosion Science· Volume 178
Publisher page

Abstract

Abstract Zr-1Nb alloy performs desired corrosion resistance in deionized water but shows accelerated corrosion in lithiated water. However, the degradation mechanism of Zr-1Nb alloy in lithiated water is still unclear. In this work, blister-like morphologies on the oxide film of the Zr-1Nb alloy corroded in lithiated water was observed, providing a direct evidence to the hydrogen generation beneath the oxide film. The formation of blisters was analysed from the perspectives of blister morphology and hydrogen uptake behaviour. A high hydrogen release rate contributes to the formation of blisters and degrades the protectiveness of oxide film and corrosion resistance after corrosion transition.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering

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References (36)

Show source-provided references
1. Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy, zirconium in the nuclear industry: twelfth international symposium
2. Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores, zirconium in the nuclear Industry: eleventh international symposium
3. Influence of water chemistry on the corrosion mechanism of a zirconium–niobium alloy in simulated light water reactor coolant conditions10.1016/j.corsci.2009.08.045 ↗
4. Oxidation behavior of β-Nb precipitates in Zr-1Nb-0.2Bi alloy corroded in lithiated water at 360°C10.1016/j.corsci.2015.07.021 ↗
5. A superior corrosion behavior of Zircaloy-4 in lithiated water at 360 ℃/18.6 MPa by β-quenching10.1016/j.jnucmat.2007.08.002 ↗
6. Analysis of the oxidized surface of 90Nb-10Zr alloy after exposure to lithiated water with 0.01M LiOH at 360°C/18.6MPa10.1016/j.corsci.2015.12.019 ↗
7. Analysis of oxidation behavior of the β-Nb phase formed in Zr–1.5Nb alloy by using the HVEM10.1016/j.jallcom.2009.03.144 ↗
8. Corrosion of M5 in PWRs quantification of Li, B, H and Nb in the oxide layers formed under different conditions10.1520/JAI103709 ↗
9. Deformation of high β-phase fraction Zr–Nb alloys at room temperature10.1016/j.actamat.2012.02.040 ↗
10. The role of hydrogen in zirconium alloy corrosion10.1016/j.jnucmat.2017.08.046 ↗
11. Lindgren · 2015 · 515
12. Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics10.1016/j.jnucmat.2014.03.001 ↗
13. Microstructure characterization of a hydride blister in Zircaloy-4 by EBSD and TEM10.1016/j.actamat.2017.03.016 ↗
14. The influence of hydride blisters on the fracture of Zircaloy-410.1016/S0022-3115(03)00299-X ↗
15. Fuel failure and fission gas release in high burnup PWR fuels under RIA conditions10.1016/S0022-3115(97)00173-6 ↗
16. Generation of destructive forces during fuel coolant interactions under severe reactivity initiated accident conditions
17. Phase and texture analysis of a hydride blister in a Zr–2.5%Nb tube by synchrotron X-ray diffraction10.1016/j.actamat.2010.12.024 ↗
18. Some unusual effects of hydrogen in corrosion reactions10.1149/1.2428575 ↗
19. A mechanism for the hydrogen uptake process in zirconium10.1016/S0022-3115(98)00492-9 ↗
20. A unified model of Zircaloy BWR corrosion and hydriding mechanisms10.1016/S0022-3115(98)00613-8 ↗
21. Effect of the second phase particles on the hydrogen absorption of Zircaloy-4 alloy corroded in super-heated steam of 400℃(in Chinese)
22. Study on the role of second phase particles in hydrogen uptake behavior of zirconium alloys10.1520/JAI102948 ↗
23. Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-410.1016/0022-3115(67)90047-5 ↗
24. Strain evolution during hydride precipitation in Zircaloy-4 observed with synchrotron X-ray diffraction10.1016/j.jnucmat.2016.01.039 ↗
25. The influence of phase and substructural evolution during dynamic loading on subsequent mechanical properties of zirconium10.1016/j.actamat.2013.09.009 ↗
26. Nodular conosion of the zircaloys, zirconium in the nuclear industry: 3rd international symposium
27. The effect of Nb on the corrosion and hydrogen pick-up of Zr alloys10.1016/j.actamat.2017.04.063 ↗
28. Corrosion-related defects in Zircaloys: a preliminary study with slow positron beam
29. Stress and defect characteristics in oxide films and corrosion resistance of Zr-1Nb alloy
30. Xu · 2014
31. Zhu · 2013
32. Yang · 2014
33. The influence of second phase particles on the crack formation in oxide films formed on zirconium alloys10.1016/j.corsci.2015.06.030 ↗
34. Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-410.1016/j.corsci.2013.05.007 ↗
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 ↗
36. Focussed ion beam sectioning for the 3D characterisation of cracking in oxide scales formed on commercial ZIRLOTM alloys during corrosion in high temperature pressurised water10.1016/j.corsci.2011.08.013 ↗