journal article·2022-04

Microstructural evolution of Cr-coated Zr-4 alloy prepared by multi-arc ion plating during high temperature oxidation

Jinghao Huang, Shuliang Zou, Weiwei Xiao, Chen Yang, Hongxing Yu, Lin Zhang, Kun Zhang

Publisher page

Abstract

To investigate the microstructural evolution during high temperature oxidation, Cr-coated Zr-4 alloy specimens are prepared by multi-arc ion plating and high temperature oxidation tests are carried out under 1000 °C, 1100 °C and 1200 °C in air atmosphere. Cr 2O 3 layers are formed on the surface after high temperature oxidation test. However, the thickness of Cr 2O 3 layer does not depend monotonously on the oxidation temperature. The oxidation temperature increases from 1000 °C to 1100 °C, the thickness of Cr 2O 3 layer increases from 2.35 μm to 5.74 μm, while the thickness is only 4.1 μm when the oxidation temperature is 1200 °C. This is mainly due to the reduction of Cr 2O 3 to Cr, and oxygen diffuses into the substrate to form α-Zr. The oxidation weight gain for the three temperatures conforms to an exponential function, while the thickness of the Cr-Zr diffusion layers follows a linear relationship with the oxidation temperature. Regarding the Zr-4 alloy substrate, the Zr grains grow up and gradually change from elongated grain parallel to the interface to elongated grain along normal direction after high temperature oxidation. Moreover, different oxidation temperatures bring distinct recrystallization energy to Zr grains, and the defects and dislocations produced during the recrystallization of Zr grain are unequal. The kernel average misorientation values obtained from EBSD indicate that the overall density of defect and dislocation of Zr grains after high temperature oxidation under 1100 °C is higher than the other two temperatures, while Zr grains after high temperature oxidation under 1000 °C has the highest local density of defect and dislocation. The investigation in this study attempts to reveal the microstructure evolution of Cr coating and Zr-4 substrate during the high temperature oxidation. These results give some new perspectives on understanding the performance of Cr-coated Zr-4 alloy under high temperature environment.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · High-Temperature Coating Behaviors

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

References (52)

Show source-provided references
1. F. Goldner, Development Strategy for Advanced LWR Fuels with Enhanced Accident Tolerance, Enhanced Accident Tolerant LWR Fuels National Metrics Workshop, Germantown, MD, October 2012.
2. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
3. Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions10.1016/j.jnucmat.2013.09.052 ↗
4. E.J. Lahoda, F.A. Boylan. Development of LWR Fuels with Enhanced Accident Tolerance. United States, October 2015.10.2172/1233713 ↗
5. Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating10.1016/j.jnucmat.2015.06.030 ↗
6. Development status of accident tolerant fuel for light water reactors in Korea10.1016/j.net.2015.11.011 ↗
7. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings10.1016/j.surfcoat.2015.09.022 ↗
8. Effect of gas pressure and bias potential on oxidation resistance of Cr coatings10.1016/j.anucene.2019.04.038 ↗
9. High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings10.1016/j.jnucmat.2019.01.039 ↗
10. Benfit or harm of accident tolerant coatings on the low-cycle fatigue properties of Zr-4 cladding alloy: in-situ studies at 400 °C10.1016/j.jnucmat.2020.152651 ↗
11. Comparative study on the tensile cracking behavior of CrN and Cr coatings for accident-tolerant fuel cladding10.1016/j.surfcoat.2020.126812 ↗
12. Chuang Dong, Microstructure, corrosion resistance and oxidation behavior of Cr-coatings on Zircaloy-4 prepared by vacuum arc plasma deposition10.1016/j.corsci.2019.06.029 ↗
13. Behavior of plasma sprayed Cr coatings and FeCrAl coatings on Zr fuel cladding under loss-of-coolant accident conditions10.1016/j.surfcoat.2018.03.016 ↗
14. Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors10.1007/s11837-017-2643-9 ↗
15. Development of Cr cold spray-coated fuel cladding with enhanced accident tolerance10.1016/j.net.2017.12.011 ↗
16. In situ-TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications10.1016/j.jnucmat.2018.10.023 ↗
17. Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding10.1016/j.jnucmat.2019.03.039 ↗
18. High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments10.1016/j.jnucmat.2019.151737 ↗
19. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-410.1016/j.jnucmat.2020.152420 ↗
20. Characterization of as-deposited cold sprayed Cr-coating on optimized ZIRLTM claddings10.1016/j.jnucmat.2021.152892 ↗
21. Semi-integral LOCA test of cold-spray chromium coated zircaloy-4 accident tolerant fuel cladding10.1016/j.jnucmat.2021.152940 ↗
22. Thermal shock resistance of TiN-, Cr-, and TiN/Cr-coated zirconium alloy10.1016/j.jnucmat.2019.151777 ↗
23. An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment10.1016/j.corsci.2019.05.017 ↗
24. Oxidation effect on pool boiling critical heat flux enhancement of Cr-coated surface for accident-tolerant fuel cladding application10.1016/j.ijheatmasstransfer.2019.118655 ↗
25. Early studies on Cr-coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
26. A systematic study of the oxidation behavior of Cr coatings on Zry4 substrates in high temperature steam environment10.1016/j.corsci.2020.108826 ↗
27. Microstructure and high-temperature steam oxidation properties of thick Cr coatings prepared by magnetron sputtering for accident tolerant fuel claddings: the role of bias in the deposition process10.1016/j.corsci.2019.108378 ↗
28. Oxidation kinetics of Cr-coated zirconium alloy: effect of coating thickness and microstructure10.1016/j.corsci.2020.108883 ↗
29. Microstructural, mechanical properties and high temperature oxidation of Cr, Al-coated Zr-4 alloy
30. Microstructure evolution and adhesion properties of thick Cr coatings under different thermal shock temperatures10.1016/j.surfcoat.2021.127224 ↗
31. Control of the preferential orientation Cr coatings deposited on zircaloy substrates and study of their oxidation behavior10.1016/j.tsf.2021.138699 ↗
32. High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment10.1016/j.jnucmat.2021.152806 ↗
33. Brachet · 2015
34. Development of Cr-coated zirconium cladding for enhanced accident tolerance
35. Behavior of chromium coated M5TM cladding under LOCA conditions
36. AREVA NP’s enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding10.1016/j.net.2017.12.004 ↗
37. Brachet · 2018
38. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process10.1016/j.corsci.2020.108537 ↗
39. Response of Cr and Cr-Al coatings on Zircaloy-2 to high temperature steam10.1016/j.jnucmat.2017.10.021 ↗
40. Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200°C10.1038/s41529-021-00155-8 ↗
41. 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 ↗
42. Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings10.1016/j.jnucmat.2018.07.063 ↗
43. Irradiation resistance of chromium coatings for ATFC in thetemperature range 300-550 °C10.1016/j.jnucmat.2021.152908 ↗
44. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux10.1016/j.nucengdes.2020.110581 ↗
45. Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings10.1016/j.anucene.2021.108206 ↗
46. Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel10.1016/j.wear.2020.203578 ↗
47. Lee · 2015
48. Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions10.1016/j.nucengdes.2019.110275 ↗
49. Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding10.1016/j.nucengdes.2020.110792 ↗
50. Effect of loading direction on the deformation and annealing behavior of a zirconium alloy10.1016/j.msea.2018.08.013 ↗
51. Supplemental literature review of binary phase diagrams: b-Fe, Cr-Zr, Fe-Np, Fe-W, Fe-Zn, Ge-Ni, La-Sn, La-Ti, La-Zr, Li-Sn, Mn-S, and Nb-Re10.1007/s11669-016-0465-z ↗
52. Supplemental literature review: o-Zr (Oxygen-Zirconium)10.1007/s11669-007-9154-2 ↗