Microstructural evolution of intermetallic phase precipitates in Cr-coated Zirconium alloy cladding in high-temperature steam oxidation up to 1400 °C
Source abstract
Abstract
The steam oxidation on the Cr-coated Zry cladding was studied up to 1400 °C to understand the oxidation behavior under the accidental conditions. The double-sided oxidation test showed that Cr coating can protect Zry cladding till 1200 °C/5 min. However, at T ≥ 1300 °C/5 min, Cr coating can no longer protect Zry cladding and the intermetallic phase of the Zr(Cr, Fe) 2 phase that precipitated within the Zry formed as globule microstructures. In addition, the transition of the intermetallic phase within the Zry substrate from the solid to liquid phases was observed, where it was determined at 1400 °C/30 min within the ZrO 2 phase.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (47)
Show source-provided references
1. S.M. Bragg-Sitton, L. Braase, R. Montgomery, C.R. Stanek, R.H. Montgomery, L.J. Ott, L.L. Snead, M.C. Billone, Enhanced accident tolerant LWR fuels: metrics development, in: Light Water Reactor Fuel Performance Meeting, Top Fuel 2013, 2013.
2. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
3. Insights from review and analysis of the Fukushima Dai-ichi accident10.1080/18811248.2011.636538 ↗
4. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
5. Microstructure, high-temperature corrosion and steam oxidation properties of Cr/CrN multilayer coatings prepared by magnetron sputtering10.1016/j.corsci.2021.109755 ↗
6. C. Tang, M. Stueber, M. Steinbrueck, M. Grosse, S. Ulrich, H.J. Seifert, Evaluation of magnetron sputtered protective Zr-Al-C coatings for accident tolerant Zircaloy claddings, in: 2017 Water Reactor Fuel Performance Meeting, 2017, pp. 1–9.
7. Review on chromium coated zirconium alloy accident tolerant fuel cladding10.1016/j.jallcom.2021.162450 ↗
8. Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C
9. Evaluation of equivalent cladding reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility10.1016/j.jnucmat.2020.152106 ↗
10. Transient experiments on oxidation and degradation of Cr-coated Zircaloy in steam up to 1600 ℃10.1016/j.corsci.2021.109805 ↗
11. Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200 °C10.1016/j.corsci.2022.110310 ↗
12. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
13. High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments10.1016/j.jnucmat.2019.151737 ↗
14. Fiber texture-dependent oxidation behaviour of Cr-coated zirconium alloy in high temperature steam10.1016/j.corsci.2022.110449 ↗
15. Y. Okada, D. Sato, K. Ogata, Y. Shinohara, N. Murakami, Investigation of chromium coated zirconium alloy behavior as accident tolerant fuel cladding for conventional LWRs, in: Proceedings of the TOPFUEL 2021, 2021.
16. The Cr-Zr system10.1007/BF02868997 ↗
17. A therrmodynamic assesment of the Cr-Zr system10.1515/ijmr-1993-840104 ↗
18. A thermodynamic database for zirconium alloys10.1016/S0022-3115(99)00125-7 ↗
19. Standard X-ray diffraction powder patterns
20. High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage10.1016/j.jnucmat.2021.153470 ↗
21. An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment10.1016/j.corsci.2019.05.017 ↗
22. High temperature oxidation of Fe-Cr alloy in O2-H2-H2O atmospheres; microstructure and kinetics10.1016/S0921-5093(03)00527-6 ↗
23. Influence of hydrogen and water vapour on the kinetics of chromium oxide growth at high temperature10.1007/s11085-011-9246-6 ↗
24. Role of water vapor in chromia-scale growth at low oxygen partial pressure10.1023/A:1023040010859 ↗
25. Microstructure, corrosion resistance and oxidation behavior of Cr-coatings on Zircaloy-4 prepared by vacuum arc plasma deposition10.1016/j.corsci.2019.06.029 ↗
26. Stresses in NiO, Cr2O3 and Al2O3 oxide scales10.1016/0921-5093(94)09747-X ↗
27. Crystal structure, corrosion kinetics of new zirconium alloys and residual stress analysis of oxide films10.1016/j.jnucmat.2009.10.055 ↗
28. The corrosion of Zr(Fe, Cr)2 and Zr2Fe secondary phase particles in Zircaloy-4 under 350 °C pressurised water conditions10.1016/j.corsci.2017.09.014 ↗
29. C. Liu, G. Li, Stacking Faults in Zr (Fe, Cr) 2 Laves Structured Secondary Phase Particle in Zircaloy-4 Alloy, 2018, pp. 249–2254. 〈https://doi.org/10.1039/c7nr08963e〉.10.1039/C7NR08963E ↗
30. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
31. Review on chromium coated zirconium alloy accident tolerant fuel cladding10.1016/j.jallcom.2021.162450 ↗
32. J.-C. Brachet, M. Le Saux, J.C. Brachet, M. Dumerval, V. Lezaud-Chaillioux, M. Le Saux, E. Rouesne, D. Hamon, S. Urvoy, T. Guilbert, Q. Houmaire, C. Cobac, G. Nony, J. Rousselot, F. Lomello, F. Schuster, H. Palancher, J. Bischoff, E. Pouillier, Behavior of Chromium Coated M5 TM Claddings under Loca Conditions R2CA H2020 EURATOM Project View Project Zr Based Nuclear Fuel Claddings Behavior upon LOCA View Project, 2017. 〈https://www.researchgate.net/publication/319988324〉.
33. Atomic-scale interface structure of a Cr-coated Zircaloy-4 material10.1007/s10853-018-2333-1 ↗
34. Characterization of as-deposited cold sprayed Cr-coating on optimized ZIRLO™ claddings10.1016/j.jnucmat.2021.152892 ↗
35. Influence of steam pressure on the high temperature oxidation and post-cooling mechanical properties of Zircaloy-4 and M5 cladding (LOCA conditions)
36. TAF-ID: an international thermodynamic database for nuclear fuels applications10.1016/j.calphad.2020.102212 ↗
37. Oxidation behavior and Cr-Zr diffusion of Cr coatings prepared by atmospheric plasma spraying on zircaloy-4 cladding in steam at 1300 °C10.1016/j.corsci.2022.110378 ↗
38. Atomic-scale interface structure of a Cr-coated Zircaloy-4 material10.1007/s10853-018-2333-1 ↗
39. High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment10.1016/j.jnucmat.2021.152806 ↗
40. Iron and chromium in Zr (Fe, Cr)2 precipitate IN Zircaloy-4
41. D. Pecheur, F. Lefebvre, A. Motta, C. Lemaignan, D. Charquet, Oxidation of intermetallic precipitates in zircaloy-4: impact of irradiation, in: Proceedings of the 10th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1245, ASTM International, West Conshohocken, PA, pp. 687–70. 〈https://doi.org/10.1520/stp15215s〉.10.1520/STP15215S ↗
42. Raman spectra of passive films of iron in neutral borate solution10.2320/matertrans1989.37.67 ↗
43. Characterization of oxide layers on SUS304L stainless steel by Raman spectroscopy10.2355/tetsutohagane1955.79.1_48 ↗
44. The Zr-Sn binary system: new experimental results and thermodynamic assessment
45. α-Zr phase field in the Zr-Sn-O system10.1016/S1359-6462(99)00135-9 ↗
46. R.R. Biederman, R.D. Sisson, J.K. Jones, W.G. Dobson, A Study of Zircaloy 4 Steam Oxidation, Technical Report EPRI-NP-734, 1978.10.2172/6863244 ↗
47. Analysis of tin diffusion in Zircaloy-4 and tin redistribution after steam oxidation by means of X-ray fluorescence measurements10.1002/adem.200800344 ↗