Effect of interface undulation on the high temperature oxidation behaviors of grit-blasted and coated zircaloy in pressurized water
Source abstract
Abstract
Abstract Effect of interface undulation on the high-temperature oxidation behaviors of grit-blasted and coated zircaloys in pressurized water was investigated. The grit-blasted and the coated zircaloy substrates present significantly higher corrosion rate than the as-received flat substrate during the early stage of exposure. Numerical analysis suggests the interface undulation results in redistribution of the oxide growth stress of zircaloy, as well as varying the local stress concentration, which induces initiation of cracks and therefore increases the corrosion rate of zircaloy. Propagation of cracks along the interface drives delamination of the protective coating. Results of this work not only promote understanding of the coating/substrate interface evolution in high-temperature pressurized water, but also provide a guide to design corrosion-resistant zirconium alloys and/or coatings for fuel cladding.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · High-Temperature Coating Behaviors · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (61)
Show source-provided references
1. Generation IV nuclear reactors: Current status and future prospects10.1016/j.enpol.2013.06.101 ↗
2. Accident tolerant fuel cladding development: Promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
3. Air oxidation of Zircaloy-4, M5® and ZIRLOTM cladding alloys at high temperatures10.1016/j.jnucmat.2011.04.012 ↗
4. Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs10.1016/j.jnucmat.2018.07.061 ↗
5. Accident tolerant FeCrAl fuel cladding: current status towards commercialization
6. Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment10.1016/j.corsci.2015.05.031 ↗
7. Microstructural characteristics of oxide films grown on Zr–0.7Sn–1Nb–0.03Fe–0.2Ge alloy corroded in lithiated water at 360 °C10.1007/s11085-014-9497-0 ↗
8. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings10.1515/corrrev-2017-0010 ↗
9. Stability of MgO-, CeO2- and SiO2-doped Cr2O3 ceramics in high-temperature supercritical water10.1016/j.corsci.2014.01.031 ↗
10. Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure10.1016/j.jnucmat.2013.03.006 ↗
11. Reactivity of Zircaloy-4 with Ti3SiC2 and Ti2AlC in the 1100–1300 °C temperature range10.1016/j.jnucmat.2015.02.006 ↗
12. Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions10.1016/j.jnucmat.2015.11.037 ↗
13. Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions10.1016/j.jnucmat.2016.10.021 ↗
14. TEM/STEM study of Zircaloy-2 with protective FeAl(Cr) layers under simulated BWR environment and high-temperature steam exposure10.1016/j.jnucmat.2018.01.055 ↗
15. Pint · 2018 · 235
16. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings10.1016/j.surfcoat.2015.09.022 ↗
17. Response of Cr and Cr-Al coatings on Zircaloy-2 to high temperature steam10.1016/j.jnucmat.2017.10.021 ↗
18. AREVA NP’s enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding10.1016/j.net.2017.12.004 ↗
19. Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance10.1016/j.net.2017.12.011 ↗
20. J. Brachet, M. Dumerval, V. Lezaud-Chaillioux, M. Le Saux, E. Rouesne, D. Hamon, et al., Behavior of chromium coated M5TM claddings under loca conditions. WRFPM. Korea, 2017.
21. J. Krejci, M. Sevecek, L. Cvrcek, Development of Chromium and Chromium Nitride Coated Cladding for VVER Reactors. WRFPM. Korea, 2017.
22. Study of the oxidation behavior of CrN coating on Zr alloy in air10.1016/j.jnucmat.2019.01.006 ↗
23. Interfacial structure, mechanical properties and thermal stability of CrAlSiN/CrAlN multilayer coatings10.1016/j.matchar.2017.01.010 ↗
24. Surface treatment to form a dispersed Y 2 O 3 layer on Zircaloy-4 tubes10.1016/j.apsusc.2017.06.108 ↗
25. Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding10.1016/j.corsci.2017.11.019 ↗
26. SiC/Si thin film deposited on zircaloy to improved accident tolerant fuel cladding10.1016/j.tsf.2018.06.006 ↗
27. Fretting wear comparison of cladding materials for reactor fuel cladding application10.1016/j.jnucmat.2018.05.069 ↗
28. Effect of Al2O3 coating on fretting wear performance of Zr alloy10.1016/j.wear.2018.12.024 ↗
29. A study of the zirconium alloy protection by Cr3C2–NiCr coating for nuclear reactor application10.1016/j.surfcoat.2015.12.088 ↗
30. Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLOTM10.1016/j.jnucmat.2018.05.014 ↗
31. Oxidation and electrochemical behaviors of Al2O3 and ZrO2 coatings on Zircaloy-2 cladding by thermal spraying10.1016/j.surfcoat.2017.11.050 ↗
32. Mechanics-based scaling laws for the durability of thermal barrier coatings10.1016/S0079-6425(00)00007-4 ↗
33. A model study of displacement instabilities during cyclic oxidation10.1016/S1359-6454(01)00403-7 ↗
34. A protocol for validating models of the cyclic undulation of thermally grown oxides10.1016/j.actamat.2005.01.006 ↗
35. Modelling of the mechanical behavior of the metal–oxide system during Zr alloy oxidation10.1016/S0022-3115(98)00045-2 ↗
36. A study into stress relaxation in oxides formed on zirconium alloys10.1016/j.jnucmat.2014.09.072 ↗
37. Transformations and cracks in zirconia films leading to breakaway oxidation of Zircaloy10.1016/j.actamat.2013.02.052 ↗
38. Residual stresses and tetragonal phase fraction characterisation of corrosion tested Zircaloy-4 using energy dispersive synchrotron X-ray diffraction10.1016/j.jnucmat.2012.07.025 ↗
39. Evolution of stress fields and phase content in corroded zirconium cladding materials10.1016/j.surfcoat.2017.05.072 ↗
40. Modelling of corrosion induced stresses during zircaloy-4 oxidation in air10.4028/www.scientific.net/MSF.595-598.419 ↗
41. Oxidation-induced creep in Zircaloy-2: III. The average stress in the oxide layer10.1016/0022-3115(81)90138-0 ↗
42. In situ measurement of stresses and phase compositions of the zirconia scale during oxidation of zirconium by raman spectroscopy10.1007/s11085-013-9433-8 ↗
43. Measurement of the crystallographically transformed zone produced by fracture in ceramics containing tetragonal zirconia10.1111/j.1151-2916.1982.tb10445.x ↗
44. Effect of oxide growth on the stress development in double-ceramic-layer thermal barrier coatings10.1016/j.ceramint.2017.07.218 ↗
45. Finite element modelling of the oxidation kinetics of Zircaloy-4 with a controlled metal-oxide interface and the influence of growth stress10.1016/j.corsci.2015.07.024 ↗
46. Chapter 2 − enabling theory
47. Comparative lattice-dynamical study of the raman spectra of monoclinic and tetragonal phases of Zirconia and Hafnia10.1111/j.1151-2916.2002.tb00346.x ↗
48. Pitting corrosion resistance of martensite of AISI 1045 steel and the beneficial role of interstitial carbon10.1149/2.0541714jes ↗
49. The effect of MEVVA implanted Cr on the corrosion resistance of CrN coated low alloy steel by cathodic arc plasma deposition10.1016/S0257-8972(03)00318-9 ↗
50. A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment10.1016/j.corsci.2015.02.027 ↗
51. Electrochemical theory of galvanic corrosion
52. Effects of surface preparation on pitting resistance, residual stress, and stress corrosion cracking in austenitic stainless steels10.1361/105994901770344638 ↗
53. Atmospheric chloride-induced stress corrosion cracking of laser engraved type 316L stainless steel10.1016/j.corsci.2018.07.016 ↗
54. Influence of surface morphology on corrosion and electronic behavior10.1016/j.actamat.2005.09.017 ↗
55. Mechanism of oxygen dissolution in metallic zirconium10.1007/BF01668512 ↗
56. The role of oxide microstructure and growth stresses in the high-temperature scaling of nickel10.1007/BF02642020 ↗
57. Godlewski · 2000 · 877
58. Study of stress effects in the oxidation of Zircaloy-410.1016/S0167-2738(01)00790-1 ↗
59. Young’s modulus, flexural strength, and fracture of yttria-stabilized zirconia versus temperature10.1111/j.1151-2916.1997.tb02920.x ↗
60. Effects of morphology on the decohesion of compressed thin films10.1016/S0921-5093(97)00848-4 ↗
61. The effect of morphology of thermally grown oxide on the stress field in a turbine blade with thermal barrier coatings10.1016/j.surfcoat.2015.06.061 ↗