Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behaviour

Tupin, Marc; Bisor, Caroline; Bossis, Philippe; Chêne, J.; Béchade, Jean-Luc; Jomard, François

doi:10.1016/j.corsci.2015.05.058

Cited by 37 publications

(23 citation statements)

References 25 publications

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“…The first one is that the hydrides precipitated beneath the metal/oxide interface in the metallic part of the cladding, resulting from the hydrogen uptake by the matrix, may be corroding at a faster rate than the metal itself [4][5][6][7]. This assumption may explain only a part of the high burnup acceleration of the alloy.…”

Section: Introductionmentioning

confidence: 99%

Influence of light ion irradiation of the oxide layer on the oxidation rate of Zircaloy-4

et al. 2015

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Section: Introductionmentioning

confidence: 99%

Influence of light ion irradiation of the oxide layer on the oxidation rate of Zircaloy-4

et al. 2015

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“…In particular, previous synchrotron XRD experiments performed on corroded pre-hydrided Zircaloy-4 have yielded information on the acceleration of corrosion due to hydride accumulation [10]. Figure 1 and Figure 2 show 3D maps obtained using micro-diffraction in scanning the sample from the metal to the resin.…”

Section: Introductionmentioning

confidence: 98%

Microstructure Evolution in Ion-Irradiated Oxidized Zircaloy-4 Studied with Synchrotron Radiation Microdiffraction and Transmission Electron Microscopy

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Tupin

et al. 2018

Zirconium in the Nuclear Industry: 18th International Symposium

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The corrosion process (oxidation and hydriding) of the zirconium alloy cladding is one of the limiting factors on the fuel rod lifetime, in particular for the Zircaloy-4 alloy. The corrosion rate of this alloy shows indeed a great acceleration at high burn-up in Light Water Reactors. Understanding the corrosion behavior under irradiation for this alloy is an important technological issue for the safety and efficiency of LWRs. In particular, understanding the effect of irradiation on the metal and the oxide layers is a key parameter in the study of corrosion behavior of zirconium alloys. Zircaloy-4 samples have undergone helium and proton ion-irradiation up to 0.3 dpa forming a uniform defect distribution up to 1 µm deep. Both as-received and pre-corroded samples have been irradiated in order to compare the effect of metal irradiation to that of oxide layer irradiation. After irradiation, samples have been corroded in order to study the impact of irradiation defects in the metal and in preexisting oxide layers on the formation of new oxide layers. Synchrotron X-ray micro-diffraction and micro-fluorescence are used to follow the evolution of oxide crystallographic phases, texture and stoichiometry both in the metal and in the oxide in cross-section. In particular, the tetragonal oxide phase fraction, which has been known to have an important role on corrosion behavior, is mapped in both unirradiated and irradiated metal at the sub-micron scale and appears to be significantly affected by irradiation. These observations, complemented with electron microscopy analyses on samples in carefully chosen areas of interest are combined in order to fully characterize changes due to irradiation in metal and oxide phases of both alloys.

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“…However, current researches generally focused on the extremely acidic mediums such as nitric, sulfuric, and hydrochloric acid, but rarely involve saline medium such as NaCl solution . Meanwhile, as the components continue to work in those saline mediums, the dissociated hydrogen would constantly adsorb and react with titanium on the surface of these components, resulting in changes in their corrosion resistance, yet there were few relevant reports . By studying the influence of hydrogenation on the electrochemical behavior of Zircaloy‐4 (Zy4) alloy, Kim et al.…”

Section: Introductionmentioning

confidence: 99%

Effect of Hydrogen Precharging on Mechanical and Electrochemical Properties of Pure Titanium

et al. 2020

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The electrolytic hydrogen precharging process is used to analyze the influence of hydrogen on the microstructure, corrosion resistance, and mechanical properties of pure titanium. The results demonstrate that two types of titanium hydrides (δ‐TiHx and ϵ‐TiH2) are detected by electron backscatter diffraction (EBSD), and the volume fraction of titanium hydrides, the local strain caused by hydrogen precipitation, and the thickness of hydrides layer increase with the increase in precharging time. It is noteworthy that the formation of hydrides layer has a protective effect on general corrosion, but the local strain caused by hydrides precipitation leads to the destruction of corrosion resistance, as a result the corrosion resistance of pure titanium increases first and then decreases with the increase in hydrogen precharging time. Moreover, with the precipitation of hydrides, the fracture mode changes from ductile failure to duplex‐ and multimode failure, resulting in the decrease in ultimate tensile strength (UTS) and elongation. Therefore, the mechanical and electrochemical properties of the precharged samples first increase and then decrease with the increase in precharging time, reaching their optimum values at 10 h, and the critical precharging time is determined to be 75 h when comparing those properties with pure titanium.

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Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behaviour

Cited by 37 publications

References 25 publications

Influence of light ion irradiation of the oxide layer on the oxidation rate of Zircaloy-4

Influence of light ion irradiation of the oxide layer on the oxidation rate of Zircaloy-4

Microstructure Evolution in Ion-Irradiated Oxidized Zircaloy-4 Studied with Synchrotron Radiation Microdiffraction and Transmission Electron Microscopy

Effect of Hydrogen Precharging on Mechanical and Electrochemical Properties of Pure Titanium

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