Effect of Zr2+ irradiation on microstructure and corrosion behavior of 90Nb-10Zr binary alloy in 360 °C lithiated water
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Abstract
Abstract The effect of Zr2+ irradiation on microstructure and corrosion in 360 °C lithiated water with 0.01 mol/L LiOH was investigated on a 90Nb-10Zr binary alloy prepared by referring to the β-Nb phase in zirconium alloys. The results revealed that the irradiation induced a ZrO2 film on the specimen surface and increased dislocations in matrix. After corrosion, oxide scales with a three-layer structure were formed regardless of irradiation. However, the scale formed on the irradiated surface was relatively thin presumably due to the ZrO2 film. A hypothesis for the corrosion mechanism of β-Nb phase in lithiated water upon irradiation was proposed.
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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
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References (57)
Show source-provided references
1. Characterization of zirconium oxides part II: new insights on the growth of zirconia revealed through complementary high-resolution mapping techniques10.1016/j.corsci.2020.108491 ↗
2. Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-410.1016/j.corsci.2013.05.007 ↗
3. Development of a cladding alloy for higher burnup
4. Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores
5. Impact of an applied stress on c-component loops under Zr ion irradiation in recrystallized Zircaloy-4 and M5®10.1016/j.jnucmat.2015.10.009 ↗
6. Out-of-pile and in-pile performance of advanced zirconium alloys (HANA) for high burn-up fuel10.1080/18811248.2006.9711185 ↗
7. Effects of alloyed Si on the autoclave corrosion performance and periodic corrosion kinetics in Zr–Sn–Nb–Fe–O alloys10.1016/j.corsci.2015.08.043 ↗
8. Study on the corrosion resistance of Zr-1Nb-xM (M=S, Cu, Ge, Bi) alloys10.1007/s11085-015-9594-8 ↗
9. Effects of laser surface alloying with Cr on microstructure and hardness of commercial purity Zr10.1016/j.jallcom.2019.01.097 ↗
10. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys10.1016/j.jnucmat.2004.09.029 ↗
11. Oxidation of Zircaloy-4 during in situ proton irradiation and corrosion in PWR primary water10.1557/jmr.2014.408 ↗
12. Hydrogen in zirconium alloys: a review10.1016/j.jnucmat.2019.02.042 ↗
13. The effects of radiation and oxygen on the aqueous oxidation of zirconium and its alloys at 290 °C10.1016/0022-3115(73)90122-0 ↗
14. Irradiation-induced amorphization in the zirconium suboxide on Zr-0.5Nb alloys10.1016/j.jnucmat.2018.11.015 ↗
15. Phase field modeling of irradiation-enhanced corrosion of Zircaloy-4 in PWRs10.1016/j.corsci.2018.10.026 ↗
16. Radiation-induced dislocation and growth behavior of zirconium and zirconium alloys – a review10.5516/NET.07.2013.035 ↗
17. The formation of bubbles in Zr alloys under Kr ion irradiation10.1016/S0022-3115(96)00757-X ↗
18. Effects of ion irradiation on microstructure and properties of zirconium alloys – a review10.1016/j.net.2014.12.015 ↗
19. Phase instability decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation10.1016/0022-3115(87)90093-6 ↗
20. Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence10.1016/0022-3115(93)90009-N ↗
21. Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy10.1016/j.jnucmat.2017.01.049 ↗
22. In situ TEM investigation of amorphization and recrystallization of Zr(Fe,Cr,Nb)2 precipitates under Ne ion irradiation10.1016/j.vacuum.2014.08.002 ↗
23. Transmission electron microscopy study of second phase particles irradiated by 2 MeV protons at 350 °C in Zr alloys10.1016/j.jnucmat.2017.07.020 ↗
24. Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys10.1016/j.actamat.2019.08.012 ↗
25. Irradiation effects on corrosion of zirconium alloy claddings10.1016/S0022-3115(97)00123-2 ↗
26. Effect of proton pre-irradiation on corrosion of Zr-0.5Nb model alloys with different Nb distributions10.1016/j.corsci.2020.108790 ↗
27. The characterisation of second phases in the Zr-Nb and Zr-Nb-Sn-Fe alloys: a critical review10.1016/j.jnucmat.2018.03.030 ↗
28. Analysis of oxidation behavior of the β-Nb phase formed in Zr-1.5Nb alloy by using the HVEM10.1016/j.jallcom.2009.03.144 ↗
29. Oxidation of β-Nb and Zr(Fe, V)2 precipitates in oxide films formed on advanced Zr-based alloys10.1016/S0022-3115(99)00253-6 ↗
30. Oxidation behavior of β-Nb precipitates in Zr-1Nb-0.2Bi alloy corroded in lithiated water at 360 °C10.1016/j.corsci.2015.07.021 ↗
31. Transmission electron microscopy examination of oxide layers formed on Zr alloys10.1016/j.jnucmat.2005.10.012 ↗
32. Influence of water chemistry on the corrosion mechanism of a zirconium-niobium alloy in simulated light water reactor coolant conditions10.1016/j.corsci.2009.08.045 ↗
33. The influence of second phase particles on the crack formation in oxide films formed on zirconium alloys10.1016/j.corsci.2015.06.030 ↗
34. Precipitation in Zr-2.5Nb enhanced by proton irradiation10.1016/0022-3115(93)90089-H ↗
35. Investigating the stability of second phase particles in Zr-Nb alloys under irradiation10.1016/j.jnucmat.2019.151738 ↗
36. Irradiation-induced Nb redistribution of ZrNb alloy: an APT study10.1016/j.jnucmat.2019.01.015 ↗
37. Study of the mechanisms controlling the oxide growth under irradiation characterization of irradiated Zircaloy-4 and Zr-1Nb-O oxide scales
38. Corrosion of electron-irradiated Zr-2.5Nb and Zircaloy-2
39. Preliminary irradiation effect on corrosion resistance of zirconium alloys
40. Optimization of N18 zirconium alloy for fuel cladding of water reactors10.1016/S1005-0302(12)60105-4 ↗
41. Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy
42. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
43. Representation of mixed reactive gases on free energy (Ellingham-Richardson) diagrams10.1007/BF02915078 ↗
44. Theory of steady-state passive films10.1149/1.2086949 ↗
45. Corrosion of phase and phase boundary in proton-irradiated 308L stainless steel weld metal in simulated PWR primary water
46. Hydrothermal synthesis and characterization of LiNbO3 crystal10.1016/j.matlet.2006.04.087 ↗
47. Analysis of the oxidized surface of 90Nb-10Zr alloy after exposure to lithiated water with 0.01 M LiOH at 360 °C/18.6 MPa10.1016/j.corsci.2015.12.019 ↗
48. The anodic oxidation of superimposed niobium and tantalum layers: theory10.1016/0013-4686(80)87156-8 ↗
49. Niobium oxides and niobates physical properties: review and prospects10.1016/j.pmatsci.2016.02.001 ↗
50. Reassessment of oxidation-induced amorphization and dissolution of Nb precipitates in Zr-Nb nuclear fuel cladding tubes10.1016/j.actamat.2017.01.032 ↗
51. Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO™ oxide layers10.1016/j.jnucmat.2014.09.073 ↗
52. Detrimental role of LiOH on the oxide film formed on Zircaloy-410.1016/j.corsci.2004.08.003 ↗
53. Phase instability under cascade damage irradiation10.1016/0022-3115(93)90120-N ↗
54. Corrosion resistances of amorphous and crystalline Zr-based alloys in simulated seawater10.1016/j.elecom.2012.08.006 ↗
55. Effect of β phase, precipitate and Nb-concentration in matrix on corrosion and oxide characteristics of Zr-xNb alloys10.1016/S0022-3115(02)01676-8 ↗
56. Influence of Nb concentration in the α-matrix on the corrosion behavior of Zr-xNb binary alloys10.1016/j.jnucmat.2003.08.031 ↗
57. Effect of neutron and ion irradiation on the metal matrix and oxide corrosion layer on Zr-1.0Nb cladding alloys10.1016/j.actamat.2019.04.055 ↗