journal article·2026-03

An integral mechanistic model for the degradation and protection loss of Cr-coated zirconium alloys in steam oxidation environments

Dongju Kim, Youho Lee

Corrosion Science· Volume 260
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

Source: Not provided · Quality: missing

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear Engineering Thermal-Hydraulics · Nuclear reactor physics and engineering

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

References (55)

Show source-provided references
1. J. Brachet, C, M. Le Saux, T. Guilbert, S. Urvoy, E. Rouesne, M. Le Flem, I. Idarraga-Trujillo, F. Schuster, F. Lomello, A. Billard, E. Monsifrot, G. Velisa, J. Bischoff, A. Ambard, Chromium coated nuclear fuel claddings for enhanced Accident Tolerant LWRs Fuel (DBA-LOCA and slightly beyond DBA-LOCA conditions, in: Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, Oak Ridge, United States, 2014.
2. AREVA NP's enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding10.1016/j.net.2017.12.004 ↗
3. Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs10.1016/j.jnucmat.2024.154915 ↗
4. Post-LOCA ductility of Cr-coated cladding and its embrittlement limit10.1016/j.jnucmat.2021.153354 ↗
5. Characterization of eutectic reaction of Cr and Cr/CrN coated zircaloy accident tolerant fuel cladding10.1016/j.net.2023.06.015 ↗
6. Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating rates10.1016/j.jnucmat.2023.154538 ↗
7. Study on eutectic melting and high-temperature oxidation characteristics of Cr coated Zr alloy cladding under steam atmosphere at 1400–1500 °C10.1016/j.jallcom.2025.183389 ↗
8. Some practical methodologies to assess the overall high temperature (one-sided) steam oxidation protectiveness of chromium-based coatings on a zirconium-based substrate, as enhanced – accident tolerant (Nuclear) fuels (E-ATF) claddings10.1016/j.jnucmat.2025.155620 ↗
9. Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200 °C10.1016/j.corsci.2022.110310 ↗
10. Steam oxidation of Cr-coated zirconium alloy claddings at 1200 °C: kinetics transition and failure mechanism of Cr coatings10.1016/j.jnucmat.2023.154684 ↗
11. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
12. Mechanisms of steam oxidation-induced degradation of chromium coating on zirconium alloys at high temperatures10.1016/j.corsci.2025.113055 ↗
13. A new «ECR» parameter to support high-temperature (one-sided) steam oxidation behavior of Cr-Coated Zr-based E-ATF claddings, in relation with their post-quenching (PQ) mechanical strength and ductility (for LOCA and slightly beyond conditions)
14. Oxidation behavior and kinetics of magnetron-sputtered Cr-coated Zr alloy cladding in 1000–1300 ℃ steam environment10.1016/j.corsci.2023.111215 ↗
15. A systematic study of the oxidation behavior of Cr coatings on Zry4 substrates in high temperature steam environment10.1016/j.corsci.2020.108826 ↗
16. An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment10.1016/j.corsci.2019.05.017 ↗
17. 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 ↗
18. Oxidation kinetics of Cr-coated zirconium alloy: effect of coating thickness and microstructure10.1016/j.corsci.2020.108883 ↗
19. Corrosion mechanism and performance of Cr-coated Zr-4 alloy in 360 °C water and 1300 °C steam10.1016/j.jmrt.2024.01.247 ↗
20. Evolution of Cr/Cr2O3 interface in Cr-coated zirconium alloy in high temperature steam10.1016/j.corsci.2023.111099 ↗
21. Fiber texture-dependent oxidation behaviour of Cr-coated zirconium alloy in high temperature steam10.1016/j.corsci.2022.110449 ↗
22. Transient experiments on oxidation and degradation of Cr-coated Zircaloy in steam up to 1600 ℃10.1016/j.corsci.2021.109805 ↗
23. Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200 ℃10.1016/j.corsci.2022.110544 ↗
24. Understanding ion transport mechanisms of chromium-coated zirconium alloy cladding in steam oxidation10.1016/j.surfcoat.2024.131123 ↗
25. Cr-O (chromium-oxygen)10.1007/s11669-997-0072-0 ↗
26. Diffusion of chromium of Cr-coated Zircaloy accident tolerant fuel cladding: Model development and experimental validation10.1016/j.surfcoat.2023.129698 ↗
27. Parabolic oxidation for various chromium-coated Zr-Nb alloy claddings10.1016/j.jnucmat.2025.155946 ↗
28. Direct experimental evidence of the reduction of Cr2O3 by Zr at high temperature10.1016/j.corsci.2023.111587 ↗
29. Diffusion and dissolution mechanism of CrSi coated Zr alloy by experiments and first principles10.1016/j.jnucmat.2025.156050 ↗
30. Degradation behavior of chromium-coated zirconium cladding under 1200 oC steam oxidation according to the coating microstructure10.1016/j.jnucmat.2024.155360 ↗
31. Effect of PEO interlayer on oxidation behavior of PEO/Cr composite coating on Zr–1 Nb alloy in 1200 °C steam
32. Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere10.1016/j.jnucmat.2023.154836 ↗
33. Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model10.1016/j.pnucene.2024.105359 ↗
34. TRANOX: model for non-isothermal steam oxidation of zircaloy cladding10.1016/j.jnucmat.2021.153153 ↗
35. Study of high burnup effect on steam oxidation of Zircaloy and its regulatory implications via the developement of a pre-transient oxide model of TRANOX10.1016/j.jnucmat.2022.153801 ↗
36. H. Kim, B. Choi, J. Park, Y. Jeong, Irradiation Properties of HANA Claddings tested in Halden Research Reactor, in: Transactions of the Korean Nuclear Society Autumn Meeting, Jeju, Korea, 2010.
37. Survey of computed grain boundary properties in face-centered cubic metals: I. Grain boundary energy10.1016/j.actamat.2009.04.007 ↗
38. A. Jaatinen, C. Achim, K. Elder, T. Ala-Nissila, 2010, Phase Field Crystal Study of Symmetric Tilt Grain Boundaries of Iron.
39. Universal function for grain boundary energies in bcc metals10.1016/j.scriptamat.2023.115821 ↗
40. Effect of oxide grain structure on the high-temperature oxidation of Cr10.1007/BF00611694 ↗
41. A short review on the phase structures, oxidation kinetics, and mechanical properties of complex Ti-Al alloys10.3390/ma14071677 ↗
42. An overview of mechanisms of the degradation of promising ATF cladding materials during oxidation at high temperatures10.1007/s11085-024-10229-y ↗
43. The kinetics of oxidation of zircaloy-4 in steam at high temperatures10.1149/1.2129227 ↗
44. Investigations of oxidation behavior and establishment of life-cycle model during the steam oxidation of Cr-coated Zry-4 at 1200 °C10.1016/j.corsci.2023.111694 ↗
45. A model for waterside oxidation of Zircaloy fuel cladding in pressurized water reactors10.1016/0022-3115(91)90487-R ↗
46. High-temperature phase diagram for the system Zr10.1111/j.1151-2916.1977.tb15557.x ↗
47. The O−Zr (Oxygen-Zirconium) system10.1007/BF02881546 ↗
48. The tetragonal-monoclinic transformation in zirconia: lessons learned and future trends10.1111/j.1551-2916.2009.03278.x ↗
49. Cladding oxidation model development based on diffusion equations and a simulation of the monoclinic-tetragonal phase transformation of zirconia during transient oxidation10.1016/j.jnucmat.2014.03.035 ↗
50. Oxygen diffusion in the oxide and alpha phases during reaction of zircaloy-4 with steam from 1000° to 1500°C10.1149/1.2129228 ↗
51. Oxidation kinetics and oxygen diffusion in low-tin Zircaloy-4 up to 1523 K10.1016/j.jnucmat.2008.03.012 ↗
52. D.L. Hagrman, G.A. Reymann, MATPRO-Version 11: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior, in, Idaho National Lab. (INL), Idaho Falls, ID (United States), United States, 1979, pp. Medium: ED.10.2172/6442256 ↗
53. Microstructures and defect structures in ZrCr2 Laves phase based intermetallic compounds10.1016/S0966-9795(02)00057-2 ↗
54. Assessment of the impact of Zr-Cr eutectic reaction on the structural integrity of Cr-coated ATF cladding10.1016/j.jnucmat.2025.156166 ↗
55. J.Y. Park, S. Kang, S. Kim, H. Jeong, K. Baek, Areas of Improvement in FRAPCON and FRAPTRAN Codes for Applications to Fuels with Cladding Material Change, in: Transactions of the Korean Nuclear Society Autumn Meeting, Jeju, Korea, 2022.10.2139/ssrn.4440953 ↗