Oxidation behavior and microstructural evolution of Zr-1.0Nb-0.01Cu during high-temperature transients
Source abstract
Abstract
To study the oxidation behavior and microstructural evolution of Zr-1.0 Nb-0.01Cu claddings during high-temperature transients simulating LOCA scenarios, samples were oxidized to 850, 900, 1000, 1100 and 1200 ℃ at heating rates of 25 and 50 ℃/min. The oxidation data show a similar trend from a parabolic to a cubic rate law. Then, the cross-sectional morphology, phase distribution, orientation, crystal structure and stress distribution were characterized. Monoclinic ZrO 2 oxide shows a fiber texture. The suboxide ZrO at the ZrO 2/Zr 3O interface from presence to absence is a continuous process with increasing temperature. The presence of ZrO could be associated with local stresses.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Intermetallics and Advanced Alloy Properties · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (64)
Show source-provided references
1. M. Billone, Y. Yan, T. Burtseva, R. Daum, Cladding Embrittlement During Postulated Loss-of-Coolant Accidents, US-NRC, NUREG-CR-6967, 2008.10.2172/946677 ↗
2. Embrittlement of pre-hydrided Zircaloy-4 by steam oxidation under simulated LOCA transients10.1016/j.jnucmat.2015.11.008 ↗
3. Pseudobinary zircaloy-oxygen phase diagram10.1016/0022-3115(79)90172-7 ↗
4. Steam oxidation of Zr–1.5Nb–0.4Sn–0.2Fe–0.1Cr and Zircaloy-4 at 900-1200℃10.1016/j.jnucmat.2006.10.015 ↗
5. Oxidation of zirconium alloys in oxygenat high temperatures up to 1600 ℃10.1007/s11085-008-9124-z ↗
6. Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600-1200 ℃10.1007/s11085-011-9249-3 ↗
7. High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding10.1016/j.jnucmat.2017.10.013 ↗
8. Simulation of oxidation phenomena during high temperature transients: application to zirconium alloys in steam10.1016/0025-5416(87)90362-4 ↗
9. Duriez · 2010
10. Numerical modeling of oxygen diffusion in the wall thickness of low-tin Zircaloy-4 fuel cladding tube during high temperature (1100-1250 ℃) steam oxidation10.1016/j.jnucmat.2010.03.004 ↗
11. Oxygen segregation in pre-hydrided Zircaloy-4 cladding during a simulated LOCA transient10.1051/epjn/2017020 ↗
12. TRANOX: model for non-isothermal steam oxidation of zircaloy cladding10.1016/j.jnucmat.2021.153153 ↗
13. Ductility loss of zircaloy cladding by inner-surface oxidation during high temperature transient10.1080/18811248.1981.9733322 ↗
14. Embrittlement behavior of zircaloy-4 cladding during oxidation and water quench10.1016/j.nucengdes.2004.08.030 ↗
15. Fracture behavior of irradiated Zircaloy-4 cladding under simulated LOCA conditions10.1080/18811248.2006.9711202 ↗
16. Behavior of high burn-up fuel cladding under LOCA conditions10.1080/18811248.2007.9711583 ↗
17. Effect of cooling rate on the residual ductility of Post-LOCA Zircaloy-4 cladding10.1016/j.jnucmat.2020.152405 ↗
18. Axial strength of Zircaloy-4 samples with reduced thickness after a simulated loss of coolant accident10.1016/j.net.2021.01.001 ↗
19. 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 ↗
20. Atom probe tomography study of alloying element distributions in Zr alloys and their oxides10.1016/j.jnucmat.2013.08.055 ↗
21. 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 ↗
22. 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 ↗
23. EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation10.1016/j.jnucmat.2015.03.043 ↗
24. Utilising DualEELS to probe the nanoscale mechanisms of the corrosion of Zircaloy-4 in 350℃ pressurised water10.1016/j.jnucmat.2015.06.022 ↗
25. In situ transmission electron microscopy study of the thermally induced formation of delta'-ZrO in pure Zr and Zr-based alloy10.1107/S160057671700680X ↗
26. 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 ↗
27. Discussion on the presence condition of suboxide ZrO beneath the oxide in zirconium alloys10.1016/j.jnucmat.2022.154011 ↗
28. Characteristics of the oxides and suboxides on Zr-1.0Nb-0.01Cu isothermally oxidised in steam at 650-1200 ℃10.1016/j.corsci.2022.110825 ↗
29. A. Garner, Investigating the Effect of Oxide Texture on the Corrosion Performance of Zirconium Alloys (D. Phil thesis), University of Manchester, 2015.
30. PTCLab: free and open-source software for calculating phase transformation crystallography10.1107/S1600576716006075 ↗
31. Thermodynamics of the Zr-O system from first principles calculations10.1103/PhysRevB.88.094108 ↗
32. Phases involved in the corrosion of zircaloy by hot water (350 ℃)10.1016/0022-3115(81)90206-3 ↗
33. X-ray studies on solid solutions of oxygen in α-Zirconium10.3891/acta.chem.scand.15-0919 ↗
34. A.T. Motta, A. Yilmazbayhan, R. Comstock, J. Partezana, G. Sabol, B. Lai, Z. Cai, Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation, in: Proceedings of the Zirconium in the Industry: 14th International Symposium, ASTM International, 2005.10.1520/STP37508S ↗
35. Instabilities in the oxidation behaviour of Zircaloy-4
36. Near coincidence site lattice misorientations in monoclinic zirconia10.1016/1359-6462(96)00303-X ↗
37. The crystal structure of baddeleyite (monoclinic ZrO2)10.1107/S0365110X59001530 ↗
38. Powder diffraction investigations of plasma sprayed zirconia10.1007/BF00375275 ↗
39. A model of texture formation in ZrO2 films10.1016/S0921-5093(02)00787-6 ↗
40. A method for accurate texture determination of thin oxide films by glancing angle laboratory X-ray diffraction10.1107/S1600576714000569 ↗
41. On Raman spectroscopy of zirconium oxide films10.1016/S0022-3115(97)00038-X ↗
42. Transformations and cracks in zirconia films leading to breakaway oxidation of Zircaloy10.1016/j.actamat.2013.02.052 ↗
43. Corrosion behaviors of Zr-Sn-Nb-Fe-Mo alloys in pure water at 360 °C/18.6 MPa: influence of annealing temperature on the anti-corrosion properties10.1016/j.corsci.2019.108255 ↗
44. Ex situ and in situ determination of stress distributions in chromium oxide films by Raman microscopy10.1016/0010-938X(92)90014-T ↗
45. 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 ↗
46. Phase transformation of oxide film in zirconium alloy in high temperature hydrogenated water10.1016/j.corsci.2015.06.034 ↗
47. Evolution of stress fields and phase content in corroded zirconium cladding materials10.1016/j.surfcoat.2017.05.072 ↗
48. In situ investigation of the oxidation of Zr-Nb-Cu alloy in high-temperature hydrogenated water10.1016/j.corsci.2017.01.013 ↗
49. High-temperature oxidation of zircaloy-4 in air studied with labeled oxygen and Raman imaging10.1007/s11085-017-9713-9 ↗
50. Review of stress fields in zirconium alloys corrosion scales10.1016/j.corsci.2015.03.004 ↗
51. Raman imaging in corrosion science: high-temperature oxidation of the zirconium alloys used in the nuclear industry as an example10.1002/jrs.6181 ↗
52. Novel compounds in the Zr-O system, their crystal structures and mechanical properties10.1039/C5CP02252E ↗
53. High-temperature stability of δ’-ZrO10.1016/j.calphad.2015.10.010 ↗
54. P. Bossis, G. Lelievre, P. Barberis, X. Iltis, F. Lefebvre, Multi-scale characterization of the metal-oxide interface of zirconium alloys, in: Proceedings of the Zirconium in the Nuclear Industry: 12th International Symposium, ASTM International, 2000.10.1520/STP14334S ↗
55. Crystal structure of the ZrO phase at zirconium/zirconium oxide interfaces10.1002/adem.201400133 ↗
56. Density functional study of the phase diagram and thermodynamic properties of Zr10.1016/j.commatsci.2010.10.017 ↗
57. Zirconium phase transformation under static high pressure and ω-Zr phase stability at high temperatures10.3390/ma12142244 ↗
58. Crystallography and a model of the α→ω phase transformation in zirconium10.1016/0001-6160(81)90152-8 ↗
59. The influence of interstitial oxygen and peak pressure on the shock loading behavior of zirconium10.1016/j.actamat.2004.12.024 ↗
60. T. Forgeron, J.C. Brachet, F. Barcelo, A. Castaing, J. Hivroz, J.P. Mardon, C. Bernaudat, Experiment and modeling of advanced fuel rod cladding behavior under LOCA conditions: alpha-beta phase transformation kinetics and EDGAR methodology, in: G.P. Sabol, G.D. Moan (Eds.), Proceedings of the Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 256–278.10.1520/STP14303S ↗
61. In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature10.1016/j.jnucmat.2014.12.067 ↗
62. The martensitic transformation in ceramics – its role in transformation toughening10.1016/S0079-6425(00)00005-0 ↗
63. Tetragonal phase stability in ZrO2 film formed on zirconium alloys and its effects on corrosion resistance10.1016/j.actamat.2006.10.030 ↗
64. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys10.1016/j.jnucmat.2004.09.029 ↗