Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg
Source abstract
Abstract
Zircaloy-2 is used as fuel cladding in commercial boiling water reactors (BWR). A limiting factor for fuel longevity is the waterside corrosion of the cladding during in-service reactor operation and associated hydrogen pickup to the alloy. It is well known that the alloying elements (such as Cr, Fe, Ni etc.) including intermetallic precipitates (also termed as SPP) distribution influences both the oxidation process and hydrogen uptake evolution in this material. This paper reports an experimental investigation on the atomic scale microstructure of nickel-containing intermetallic particles with an emphasis on the oxidation and nickel-dissolution of SPP, and a combined experimental and computational study of solute nickel located in the corroded zirconium oxide microstructure. An irradiated cladding sample, taken from a BWR fuel rod, was prepared for the analysis using electron probe microanalysis (EPMA) and synchrotron-based micro-beam X-ray techniques (μXRF, μXRD and μXAS). The results show that the Ni-bearing SPP in the oxide layer are neither fully dissolved nor entirely oxidized at the given burn-up of the sample investigated. Conversely, all solute nickel present in the corroded layer is mostly oxidized and has an apparent homogeneous Ni2+distribution. By analyzing the μXAS spectra measured at the Ni absorption edge, we have obtained quantitative structural information about both irradiated SPP and the Ni coordination environment in the corrosion layer. There exists strong structural disorder in intermetallic Ni-bearing SPP as also evidenced by μXRD study. The basic structure away from SPP in the oxide area is composed of oxidized nickel atoms adjacent to oxygen vacancies. Finally, first-principles density functional theory (DFT) calculations have been used to discern the nickel speciation in zirconium oxide microstructure that is complementary to the multitude of experimental information. From this joint theoretical and experimental approach, significant insights into the structural specificity of Ni2+ions in monoclinic ZrO2, electronic factors governing the electron transport processes in the corrosion layer, and the apparent influence of nickel on the hydrogen ingress behavior in Zircaloy-2 are obtained.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (65)
Show source-provided references
1. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
2. Oxidation and hydrogen uptake in zirconium, Zircaloy-2 and Zircaloy-4: computational thermodynamics and ab initio calculations10.1016/j.jnucmat.2013.09.038 ↗
3. Micro-focussed XAFS spectroscopy to study Ni-bearing precipitates in the metal of corroded Zircaloy-210.1007/s00339-009-5456-z ↗
4. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys10.1016/j.jnucmat.2004.09.029 ↗
5. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
6. Barrier oxide chemistry and hydrogen pick-up mechanisms in zirconium alloys10.1016/j.corsci.2015.11.002 ↗
7. ASTM STP 1423Alternative Zr Alloys With Irradiation Resistant Precipitates for High Burnup BWR Application, Zirconium in the Nuclear Industry: Thirteenth International Symposium2002
8. Oxidation behaviour of binary zirconium alloys containing intermetallic precipitates10.1016/j.jnucmat.2010.11.099 ↗
9. Analytical investigations of irradiated inert matrix fuel10.1016/j.jnucmat.2008.12.030 ↗
10. Microprobe analysis of neutron irradiated and autoclaved zirconium niobium claddings using synchrotron-based hard X-ray imaging and spectroscopy10.1016/j.jnucmat.2008.12.022 ↗
11. Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding10.1016/j.jnucmat.2017.03.010 ↗
12. Investigation of irradiated uranium-plutonium mixed oxide fuel by synchrotron based micro X-ray diffraction10.1016/j.pnucene.2011.11.012 ↗
13. Local atomic structure of chromium bearing precipitates in chromia doped uranium dioxide investigated by combined micro-beam X-ray diffraction and absorption spectroscopy10.1016/j.jnucmat.2014.03.017 ↗
14. A commercial software package MATLAB, The MathWorks Inc., Natick, MA, USA.
15. Calibration and correction of spatial distortions in 2D detector systems10.1016/0168-9002(94)90720-X ↗
16. Micro X-ray diffraction and fluorescence tomography for the study of multilayered automotive paints10.1002/sia.3125 ↗
17. http://www.crystalimpact.com/match.
18. HEPHAESTUS: data analysis for X-ray absorption spectroscopy using IFEFFIT10.1107/S0909049505012719 ↗
19. Theoretical X-ray Absorption Fine Structure Standards10.1021/ja00014a001 ↗
20. Recent observations on the evolution of the second phase particles in Zircaloy-2 under irradiation in a BWR up to a high burn-up
21. Shielded field emission EPMA for microanalysis of radioactive materials
22. Effects of secondary phase particle dissolution on the in-reactor performance of BWR cladding10.1520/JAI103025 ↗
23. Microbeam X-ray absorption spectroscopy study of chromium in large-grain uranium dioxide fuel
24. ASTM STP 1543Understanding the Drivers of in-Reactor Growth of β-Quenched Zircaloy-2 BWR Channels, Zirconium in the Nuclear Industry: 17th International Symposium2015
25. BWR Zircaloy cladding corrosion behavior - effect of microstructure10.1016/S0022-3115(97)00124-4 ↗
26. The maturing of nuclear fuel: past to accident tolerant fuel10.1016/j.pnucene.2017.07.016 ↗
27. Effects of hydride precipitate localization and neutron fluence on the ductility of irradiated Zircaloy-4
28. Structural characterization study of nickel ferrite particles dispersed in a corrosion product deposit layer10.1016/j.apsusc.2010.08.052 ↗
29. Corrections for matrix effects in X-ray fluorescence analysis – a tutorial10.1016/j.sab.2006.06.014 ↗
30. Residual stress distribution in oxide films formed on Zircaloy-210.1016/j.jnucmat.2015.08.040 ↗
31. 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 ↗
32. Porosity in oxides on zirconium fuel cladding alloys and its importance in controlling oxidation rates10.1016/j.scriptamat.2009.12.043 ↗
33. Waterside corrosion in zirconium alloys10.1007/s11837-011-0140-0 ↗
34. The measurement of stress and phase fraction distributions in pre and post-transition Zircaloy oxides using nano-beam synchrotron X-ray diffraction10.1016/j.jnucmat.2016.07.024 ↗
35. National Institute of Standards and Technology · 2018
36. Jandel Scientific, PeakFit v2.01.
37. Second phase particles in zircaloy-210.1016/0022-3115(89)90573-4 ↗
38. Synchrotron radiation study of second-phase particles and alloying elements in Zirconium alloys
39. Effects of thermal annealing on the macroscopic dimension and lattice parameter of heavily neutron-irradiated silicon carbide10.1080/18811248.1992.9731578 ↗
40. X-ray absorption spectroscopy study of the Ni K edge in magnetron sputtered nickel oxide thin films10.1088/0953-8984/9/32/019 ↗
41. Local Valence and hole doping effect on magnetic properties in double perovskite La2NiMnO610.1007/s10948-013-2168-6 ↗
42. New oxides of the filled-Ti2Ni type structure10.1016/0925-8388(94)90079-5 ↗
43. Persson · 2014
44. See for example: P. Li, I.W. Chen, J.E. Penner-Hahn, X-ray-absorption studies of zirconia polymorphs: Characteristic local structures, Phys. Rev. B48 (1993) 10063-73.10.1103/PhysRevB.48.10063 ↗
45. Optical properties of Ni2+ in ZrO2 nanocrystals10.1016/j.optmat.2004.04.003 ↗
46. Ab initio molecular dynamics for liquid metals10.1103/PhysRevB.47.558 ↗
47. Efficient iterative schemes for ab initio total-energy calculations using a plane-wave basis set10.1103/PhysRevB.54.11169 ↗
48. First-principles calculations to describe zirconia pseudopolymorphs10.1103/PhysRevB.59.4044 ↗
49. Structural, electronic, and optical properties of ZrO2 from ab initio calculations10.1063/1.2386967 ↗
50. Vosko · Can. J. Phys. · 1980 · 54 · 120010.1139/p80-159 ↗
51. Generalized gradient approximation made simple10.1103/PhysRevLett.77.3865 ↗
52. Enhanced oxygen buffering by substitutional and interstitial Ni point defects in Ceria: a first-principles DFT+U study10.1021/jp101100f ↗
53. Linear response approach to the calculation of the effective interaction parameters in the LDA+U method10.1103/PhysRevB.71.035105 ↗
54. Structural properties and quasiparticle band structure of zirconia10.1103/PhysRevB.57.7027 ↗
55. Phonons and lattice dielectric properties of zirconia10.1103/PhysRevB.65.075105 ↗
56. Bonding and electronic structure in zirconia pseudopolymorphs investigated by electron energy-loss spectroscopy10.1103/PhysRevB.54.7094 ↗
57. Effect of metallographic factor on hydrogen pick-up properties of Zircaloy-210.1080/18811248.2006.9711186 ↗
58. A study of the hydrogen uptake mechanism in Zirconium alloys
59. Hydrogen accommodation in Zr second phase particles: implications for H pick-up and hydriding of Zircaloy-2 and Zircaloy-410.1016/j.corsci.2012.11.036 ↗
60. A unified model of Zircaloy BWR corrosion and hydriding mechanisms10.1016/S0022-3115(98)00613-8 ↗
61. Barrier oxide chemistry and hydrogen pick-up mechanisms in zirconium alloys10.1016/j.corsci.2015.11.002 ↗
62. Oxygen vacancy formation, mobility and hydrogen pick-up during oxidation of zirconium by water10.1007/s11085-016-9695-z ↗
63. Impact of additives on zirconium oxidation by water: mechanistic insights from first principles10.1039/c3ra42941e ↗
64. Possible origin of nano-porosity in ZrO2 scales for hydrogen pick-up in Zr alloys10.1016/j.jnucmat.2017.05.017 ↗
65. Oxidation of Zr alloys by water – theory from first principles