Thermal decomposition behavior of ZrO2 barrier layer against Cr/Zr inter-diffusion under high temperature
Source abstract
Abstract
The Cr/Zr inter-diffusion has been becoming a critical issue for Cr-coated Zr alloys as accident tolerant fuel (ATF) cladding. Here, ZrO 2 barrier layers against Cr/Zr inter-diffusion were successfully fabricated between the Cr layer and Zry4 substrate. Thermal decomposition of ZrO 2 is confirmed under high temperatures, and ZrO 2 is transformed into oxygen-stabilized α-Zr (O), which is effective for mitigating the Cr/Zr inter-diffusion. In-situ transmission electron microscopy (TEM) results indicate that the ZrO 2 thermal decomposition process becomes more obvious under 500 °C. In addition, Cr/ α-Zr (O) inter-diffusion leads to the thin Zr(Cr, Fe) 2 interface layer due to the high stability of the α-Zr (O) phase.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (39)
Show source-provided references
1. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings10.1016/j.surfcoat.2015.09.022 ↗
2. Early studies on CrCoated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
3. Review on chromium coated zirconium alloy accident tolerant fuel cladding10.1016/j.jallcom.2021.162450 ↗
4. Improved irradiation resistance of Cr-Fe alloy for Cr-coated Zircaloy application in accident tolerant fuel10.1016/j.scriptamat.2023.115344 ↗
5. Designing radiation resistance in materials for fusion energy10.1146/annurev-matsci-070813-113627 ↗
6. A systematic study of the oxidation behavior of Cr coatings on Zry4 substrates in high temperature steam environment10.1016/j.corsci.2020.108826 ↗
7. Direct experimental evidence of the reduction of Cr2O3 by Zr at high temperature10.1016/j.corsci.2023.111587 ↗
8. Experimental kinetic study of interdiffusion behavior and intermetallic compound Zr (Fe,Cr)2 formation at the Cr/Zry4 interface under elevated temperatures
9. High temperature steam oxidation of chromium-coated zirconium based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
10. Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors10.1007/s11837-017-2643-9 ↗
11. 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 ↗
12. Growth kinetics and microstructure characteristics of the Zr-Cr interlayer in a Cr-coated Zry-4 alloy exposed to high-temperature steam10.1016/j.corsci.2023.111600 ↗
13. High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment10.1016/j.jnucmat.2021.152806 ↗
14. Microstructure evolution and mechanical property of high temperature solid-state diffusion bonded Cr-Zry4 with and without a 316 SS interlayer
15. Development and testing of multicomponent fuel cladding with enhanced accidental performance10.1016/j.net.2019.08.015 ↗
16. Microstructural understanding of CrN layer as a barrier against Cr-Zr interdiffusion in Cr-coated zirconium alloy for accident tolerant fuel claddings10.1016/j.matchar.2023.113242 ↗
17. Diffusion and oxidation behavior of Cr-ZrN coated Zr alloy accident tolerant fuel cladding materials at high temperature
18. High- Temperature Steam Oxidation of Accident-tolerant Cr/Mo-coated Zr Alloy at 1200-1400 °C10.3390/coatings13010191 ↗
19. Investigation of inter diffusion behavior in the Mo–Zr binary system via diffusion couple studies10.1016/j.ijrmhm.2013.12.017 ↗
20. Analyses of hydrogen release on zirlo alloy anode during plasma electrolytic oxidation10.1016/j.matchemphys.2020.123054 ↗
21. Analyses of electrochemical behavior of plasma electrolytic oxidation film on Zirlo alloy in lithium borate buffer solution at 25-300 °C10.1016/j.surfcoat.2021.127935 ↗
22. Effects of Li, B and H elements on corrosion property of oxide films on ZIRLO alloy in 300°C/14 MPa lithium borate buffer solutions10.1016/j.corsci.2020.109216 ↗
23. Enhancement of high temperature steam oxidation resistance of Zr–1Nb alloy with ZrO2/Cr bilayer coating10.1016/j.corsci.2021.109494 ↗
24. TEM characterizations of a ZrO2/Cr composite coating on Zr-1Nb alloy after 1200 °C steam oxidation10.1016/j.matchar.2023.112701 ↗
25. J. Stuckert, M.S. Veščunov, Behaviour of oxide layer of zirconium-based fuel rod cladding under steam starvation conditions, (2008).
26. Microstructural evolution of pre-oxidized Cr-coated Zry-4 during annealing in argon10.1016/j.jnucmat.2022.154144 ↗
27. Protective Cr coatings with ZrO2/Cr multilayers for zirconium fuel claddings10.3390/coatings12101409 ↗
28. A practical guide to pulsed laser deposition10.1039/D2CS00938B ↗
29. Thermal stability of the Cr-coated zirconium alloy microstructure prepared by pulsed laser deposition10.1007/s42864-023-00235-z ↗
30. High-temperature reaction of oxygen-stabilized α-Zr (O) with nitrogen10.1016/j.jnucmat.2013.12.024 ↗
31. Diffusion of oxygen in zirconium and its relation to oxidation and corrosion10.1149/1.2428837 ↗
32. On the solubility of Fe, Cr and Nb in ZrO2 and its effect on thermal dilatation and polymorphic transition10.1016/0025-5408(90)90146-S ↗
33. Effects of He and Ni ion irradiation on the ZrO2/Cr composite coating on Zr1Nb alloy10.1016/j.jallcom.2023.172622 ↗
34. Diffusion bonding of a nickel (chromium) alloy to zirconia: mechanical properties and interface microstructures10.1007/BF01154944 ↗
35. The formation and stacking faults of Fe and Cr containing Laves phase in Zircaloy-4 alloy10.1016/j.matlet.2016.12.062 ↗
36. Stacking faults in Zr(Fe,Cr)2 Laves structured secondary phase particle in Zircaloy-4 alloy10.1039/C7NR08963E ↗
37. Cross stacking faults in Zr(Fe,Cr)2 face-centered cubic Laves phase nanoparticle10.1016/j.apsusc.2020.145716 ↗
38. Microstructure of Zircaloy-4 alloy during β phase quenching and determination of critical quenching diameter of its rods10.1016/j.nme.2018.10.014 ↗
39. Oxidation resistance improvement of Zr-4 alloy in 1000 °C steam environment using ZrO2/FeCrAl bilayer coating10.1016/j.surfcoat.2018.05.005 ↗