Hydrogen absorption cracking of zirconium alloy in the application of nuclear industry

Zhao, Chao; Song, Xiping; Yang, Yun; Zhang, Bei

doi:10.1016/j.ijhydene.2013.01.009

Cited by 31 publications

(15 citation statements)

References 24 publications

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“…However, in another research, except for some specimens with high H concentration at room temperature, the macroscopic fracture behavior was ductile [38]. At the grain size below 30 µm, the cracks were small and independent, while above 500 µm of grain size, they became more abundant [54].…”

mentioning

confidence: 84%

Hydrogen Embrittlement and Oxide Layer Effect in the Cathodically Charged Zircaloy-2

et al. 2020

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The present paper is aimed at determining the less investigated effects of hydrogen uptake on the microstructure and the mechanical behavior of the oxidized Zircaloy-2 alloy. The specimens were oxidized and charged with hydrogen. The different oxidation temperatures and cathodic current densities were applied. The scanning electron microscopy, X-ray electron diffraction spectroscopy, hydrogen absorption assessment, tensile, and nanoindentation tests were performed. At low oxidation temperatures, an appearance of numerous hydrides and cracks, and a slight change of mechanical properties were noticed. At high-temperature oxidation, the oxide layer prevented the hydrogen deterioration of the alloy. For nonoxidized samples, charged at different current density, nanoindentation tests showed that both hardness and Young’s modulus revealed the minims at specific current value and the stepwise decrease in hardness during hydrogen desorption. The obtained results are explained by the barrier effect of the oxide layer against hydrogen uptake, softening due to the interaction of hydrogen and dislocations nucleated by indentation test, and hardening caused by the decomposition of hydrides. The last phenomena may appear together and result in hydrogen embrittlement in forms of simultaneous hydrogen-enhanced localized plasticity and delayed hydride cracking.

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mentioning

confidence: 84%

Hydrogen Embrittlement and Oxide Layer Effect in the Cathodically Charged Zircaloy-2

et al. 2020

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“…The surface preparation was developed based on such far reports, in which different procedures were proposed, from the grinding with the No. 1,200 paper [37] to the paper No. 5,000 and diamond paste 0.5 µm [4].…”

Section: Methodsmentioning

confidence: 99%

“…At the grain size below 30 µm, the cracks were small and independent, while above 500 µm they became larger and propagated along the radial direction. Not only large cracks but also small bulges were observed [37]. The ductile fracture showed some dimples associated with ductile metallic ligaments [17].…”

Section: Hydrogen Degradationmentioning

confidence: 97%

Hydrogen degradation of pre-oxidized zirconium alloys

Szoka

Gajowiec

Zieliński

et al. 2017

Advances in Materials Science

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The presence of the oxide layers on Zr alloys may retard or enhance the hydrogen entry and material degradation, depending on the layer features. This research has been aimed to determine the effects of preoxidation of the Zircaloy-2 alloy at a different temperature on hydrogen degradation. The specimens were oxidised in laboratory air at 350ºC, 700ºC, and 900ºC. After, some samples were tensed at 10-5 strain rate and simultaneously charged with hydrogen under constant direct voltage in 1 N sulfuric acid at room temperature. Other specimens were charged without any tension, then annealed at 400ºC for 4 h and finally tensed at above strain rate. The SEM examinations were performed on the cross-sections and fracture faces of specimens. The obtained results demonstrate the effects of the oxide layer on the cathodic current and hydrogen entry, mechanical properties and the appearance of hydrides and fracture behaviour.

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“…Therefore, compared with the usual hydrogen loading techniques [5,6], hydrogenation in a D-D neutron generator is achieved by accelerating D + to a desired energy and then implanting it into the desired region, making a highly inhomogeneous local distribution of hydrogen isotopes. Although a series of studies to understand the mechanisms of zirconium hydrogenation have been conducted with ordinary hydrogen loading techniques, such as electrochemical charging and thermal absorption [7,8], reports concerning hydrogenation of zirconium by ion implantation are rare. Therefore, it is important to investigate this kind of hydrogenation to understand the mechanisms of the interaction between the beam and target in a drive-in D-D neutron generator.…”

Section: Introductionmentioning

confidence: 99%

Hydrogenation of zirconium film by implantation of hydrogen ions

Liu¹,

Fang

2017

Plasma Sci. Technol.

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In order to understand the drive-in target in a D-D type neutron generator, it is essential to study the mechanism of the interaction between hydrogen ion beams and the hydrogen-absorbingmetal film. The present research concerns the nucleation of hydride within zirconium film implanted with hydrogen ions. Doses of 30 keV hydrogen ions ranging from 4.30×10 17 to 1.43×10 18 ions cm −2 were loaded into the zirconium film through the ion beam implantation technique. Features of the surface morphology and transformation of phase structures were investigated with scanning electron microscopy, atomic force microscopy and x-ray diffraction. Confirmation of the formation of δ phase zirconium hydride in the implanted samples was first made by x-ray diffraction, and the different stages in the gradual nucleation and growth of zirconium hydride were then observed by atomic force microscope and scanning electron microscopy.

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Hydrogen absorption cracking of zirconium alloy in the application of nuclear industry

Cited by 31 publications

References 24 publications

Hydrogen Embrittlement and Oxide Layer Effect in the Cathodically Charged Zircaloy-2

Hydrogen Embrittlement and Oxide Layer Effect in the Cathodically Charged Zircaloy-2

Hydrogen degradation of pre-oxidized zirconium alloys

Hydrogenation of zirconium film by implantation of hydrogen ions

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