Enhancement of oxidation resistance of zirconium alloy with anodic nanoporous oxide layer in high-temperature air/steam environments
Source abstract
Abstract
Abstract Highly-ordered and hexagonally close-packed nanoporous zirconium oxide layer is formed on the surface of zirconium alloy by anodization, and the anti-oxidation behavior of the zirconium alloy with the nanoporous oxide layer has been investigated. The oxidation experiments were carried out in both air and steam environments at 1000 °C. Interestingly, zirconium alloy with the nanoporous oxide layer exhibits dramatic improvement in the oxidation resistance compared to bare zirconium alloy without the nanoporous oxide layer. Analysis using several characterization tools reveals that large single-crystalline columnar zirconium oxide grains are formed beneath the nanoporous oxide layer and these grains prevent further oxidation.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · High-Temperature Coating Behaviors
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (37)
Show source-provided references
1. Comparison of the Chernobyl and Fukushima nuclear accidents: a review of the environmental impacts10.1016/j.scitotenv.2013.10.029 ↗
2. Isotopic evidence of plutonium release into the environment from the Fukushima DNPP accident10.1038/srep00304 ↗
3. Chemical compatibility between UO2 fuel and SiC cladding for LWRs. Application to ATF (accident-tolerant fuels)10.1016/j.jnucmat.2017.02.031 ↗
4. Forward for special JNM issue on accident tolerant fuels for LWRs preface10.1016/j.jnucmat.2014.03.030 ↗
5. Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes10.1051/epjn/2016012 ↗
6. 2nd special JNM issue on accident tolerant fuels for LWRs10.1016/j.jnucmat.2015.08.028 ↗
7. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
8. Structural materials challenges for advanced reactor systems10.1016/j.jnucmat.2008.11.026 ↗
9. Radiation effects in SiC for nuclear structural applications10.1016/j.cossms.2012.03.005 ↗
10. Characteristics of composite silicon carbide fuel cladding after irradiation under simulated pwr conditions10.13182/NT12-86 ↗
11. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding10.1016/j.jnucmat.2013.06.041 ↗
12. High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments10.1016/j.jnucmat.2013.05.047 ↗
13. Improving accident tolerance of nuclear fuel with coated Mo-alloy cladding10.1016/j.net.2015.12.003 ↗
14. Hydrogen permeation in FeCrAl alloys for LWR cladding application10.1016/j.jnucmat.2015.02.040 ↗
15. Self-organized porous titanium oxide prepared in H2SO4/HF electrolytes10.1149/1.1545192 ↗
16. Formation of self-organized niobium porous oxide on niobium10.1016/j.elecom.2004.11.012 ↗
17. Self-assembled porous tantalum oxide prepared in H2SO4/HF electrolytes10.1149/1.1859676 ↗
18. Self-organized porous WO3 formed in NaF electrolytes10.1016/j.elecom.2005.01.003 ↗
19. Self-organized nanotubular oxide layers on Ti-6A1-7Nb and Ti-6A1-4V formed by anodization in NH4F solutions10.1002/jbm.a.30501 ↗
20. TiO2-Nb2O5 nanotubes with electrochemically tunable morphologies10.1002/anie.200601957 ↗
21. Controlled fabrication of nanoporous oxide layers on zircaloy by anodization10.1186/s11671-015-1086-x ↗
22. High-temperature oxidation behavior of zircaloy-4 and zirlo in steam ambient10.1016/S1005-0302(10)60132-6 ↗
23. Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation10.1016/j.jnucmat.2007.02.011 ↗
24. Zircaloy-4 and M5® high temperature oxidation and nitriding in air10.1016/j.jnucmat.2008.07.002 ↗
25. Air oxidation of Zircaloy-4, M5 (R) and ZIRLO (TM) cladding alloys at high temperatures10.1016/j.jnucmat.2011.04.012 ↗
26. Raman investigation of pre- and post-breakaway oxide scales formed on Zircaloy-4 and M5® in air at high temperature10.1016/j.jnucmat.2011.11.071 ↗
27. Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures10.1016/j.jnucmat.2009.04.018 ↗
28. Oxidation kinetics of Zircaloy-4 and Zr–1Nb–1Sn–0.1Fe at temperatures of 700–1200°C10.1016/j.jnucmat.2004.08.007 ↗
29. Weld bead size, microstructure and corrosion behavior of zirconium alloys joints welded by pulsed laser spot welding10.1007/s11665-016-2250-x ↗
30. Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate10.1016/j.jnucmat.2003.08.038 ↗
31. Effects of the accumulated annealing parameter on the corrosion characteristics of a Zr-0.5Nb-1.0Sn-0.5Fe-0.25Cr alloy10.1016/S0022-3115(99)00288-3 ↗
32. Tetragonal phase stability in ZrO2 film formed on zirconium alloys and its effects on corrosion resistance10.1016/j.actamat.2006.10.030 ↗
33. Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO (TM) oxide layers10.1016/j.jnucmat.2014.09.073 ↗
34. Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-410.1016/j.corsci.2013.05.007 ↗
35. Transmission electron microscopy examination of oxide layers formed on Zr alloys10.1016/j.jnucmat.2005.10.012 ↗
36. The tetragonal-monoclinic transformation in zirconia: lessons learned and future trends10.1111/j.1551-2916.2009.03278.x ↗
37. Analysis on volume fraction and crystal orientation relationship of monoclinic and tetragonal oxide grown on Zr-2.5Nb alloy10.1016/j.jnucmat.2004.06.003 ↗