Influence of ions irradiation on the microstructural evolution, mechanical and tribological properties of Zr-4 alloy

Jiang, Haixia; Duan, Zewen; Zhao, Xiaoyu; Zhang, Beibei; Wang, Peng

doi:10.1016/j.apsusc.2019.143821

Cited by 20 publications

(7 citation statements)

References 31 publications

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“…During the deformation of the material, these defects exert a pinning effect on dislocations within the matrix, impeding their mobility. Consequently, this impediment culminates in material hardening, thereby augmenting the material's hardness (Jiang et al , 2019). The average surface hardness of TC4 alloy in three different environments is also shown in the figure, ranging from 500 to 900 nm.…”

Section: Resultsmentioning

confidence: 99%

“…Additionally, the diffraction peak width of the sample increased after PI, attributed to gaps, amorphousness, and vacancies on the surface of the TC4 alloy. The absence of oxides in the GIXRD results of AO samples can be explained by the experimental condition of grazing angle 3°, representing an X-ray characterization depth of 1344 nm (Jiang et al , 2019), which significantly exceeds the thickness of the oxide film.…”

Section: Resultsmentioning

confidence: 99%

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Multi-scale wear mechanism of material surface and hinge interface based on TC4 alloy in space environment

Wang,

Huang,

et al. 2024

ILT

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Purpose The purpose of this paper is to clarify the influence of low earth orbit space environment on the wear mechanism of TC4 alloy material and crank rocker mechanism. Design/methodology/approach In this study, friction experiments were carried out on TC4 alloy friction discs and crank rocker mechanisms, both before and after exposure to atomic oxygen and proton irradiation. Nanoindentation, grazing incidence X-ray diffraction (GIXRD), and X-ray photoelectron spectroscopy were employed to systematically characterize alterations in mechanical properties, surface phase, and chemical composition. Findings The results show that the wear mechanism of TC4 alloy friction disc is mainly adhesive wear in vacuum environment, while the wear mechanism of crank rocker mechanism includes not only adhesive wear but also abrasive wear. Atomic oxygen exposure leads to the formation of more oxides on the surface of TC4 alloy, which form abrasive particles during the friction process. Proton irradiation will lead to a decrease in fatigue performance and an increase in hardness on the surface of TC4 alloy, thus causing fatigue wear on the surface of TC4 alloy, and more furrows appear on the crank rocker mechanism after proton irradiation. In the three environments, the characteristics of abrasive wear of the crank rocker mechanism are more obvious than those of the TC4 alloy friction disc. Originality/value These results highlight the importance of understanding the subtle effects of atomic oxygen and proton irradiation on the wear behavior of TC4 alloy and provide some insights for optimizing its performance in space applications. Peer review The peer review history for this article is available at: https://publons.com/publon/10.1108/ILT-02-2024-0051/

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Multi-scale wear mechanism of material surface and hinge interface based on TC4 alloy in space environment

Wang,

Huang,

et al. 2024

ILT

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“…Zr alloy tube can isolate the outside primary circuit water from the inside uranium pellets, and thus, it can be regarded as one of the most significant barriers to prevent nuclear leakage in the reactor [4]. However, Zr alloy tube in the reactor would suffer high-temperature aqueous corrosion, irradiation damage and hydrogen-induced cracking due to the harsh and intricate service environment [5][6][7][8], which would cause the reduction of its service life. In addition, fretting wear between Zr alloy tubes and grids occurs inevitably during pressurized water reactor (PWR) operation because of the flow-induced vibration (FIV) and the installation feature [9][10][11], which would cause tube perforation and bring destructive consequences to the reactor [12,13].…”

Section: Introductionmentioning

confidence: 99%

Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR

Zhang

Jiang

Ming

et al. 2022

Acta Metall. Sin. (Engl. Lett.)

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The effect of normal force on fretting wear behavior of zirconium alloy tube mated with grid dimple in simulated primary water of pressurized water reactor nuclear power plant was investigated. Results showed that the maximum wear depth, wear volume and wear coefficient of Zr alloy tube in simulated primary water at 315 °C gradually increased with increasing normal force, while the friction coefficient gradually decreased. Fretting process could be divided into four stages according to the variation of friction coefficient during test. When normal force exceeds 30 N, the fretting regime would transition from gross slip regime to partial slip regime after 3 × 10 7 cycles. Delamination was aggravated with increasing normal force, while abrasive wear became slighter. A thicker third-body layer with monoclinic ZrO 2 was formed by the tribo-sintering mechanism under higher normal force. In addition, the schematic evolution processes of delamination and third-body layer formation were displayed according to morphology observation. Keywords Zirconium alloy tube • Fretting wear • Grid-to-rod • High-temperature pressurized water • Normal force

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“…For example, factors, such as the flow of cooling water [13], the magnitude of the load [14], and the magnitude of the sliding [15], affect the wear of Zr-4 alloys. In addition, Jiang et al [16,17] studied the wear properties of Zr-4 alloy tubes before and after irradiation, and found that the friction mechanism would change from adhesive wear combined with abrasive wear to abrasive wear combined with fatigue brittle fracture, and the fracture of wear debris after irradiation and spalling aggravate the wear of Zr-4 alloy. Tang et al [18] showed that the oxide film formed after oxidation can effectively reduce the wear depth and friction coefficient of Zr-4 alloy cladding.…”

Section: Introductionmentioning

confidence: 99%

Effect of Impact Velocity and Angle on Impact Wear Behavior of Zr-4 Alloy Cladding Tube

Liu

et al. 2022

Materials

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In the pressurized water reactor nuclear power plant, 316L SS chips were captured by the support grid and continued to affect the Zr-4 cladding tube, causing the fuel rods to wear and perforate. In this work, a 60° acute angle cone of 316L SS was used to simulate the cyclic impact of debris on a Zr-4 alloy tube with different initial impact velocities and impact angles. Results showed that increasing the initial impact velocity will generate a wear debris accumulation layer with a wear-reducing effect, but also promote the extension and expansion of fatigue cracks, resulting in the delamination of Zr-4 alloy tubes. The inclination of the impact angle increases the energy loss. The energy loss rate of the 45° impact is as high as 69.68%, of which 78% is generated by the impact-sliding stage. The normal force is mainly responsible for the wear removal and plastic deformation of Zr-4 alloy tubes. Tangential forces cause severe cutting in Zr-4 alloys and pushes the resulting wear debris away from the contact surfaces.

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Influence of ions irradiation on the microstructural evolution, mechanical and tribological properties of Zr-4 alloy

Cited by 20 publications

References 31 publications

Multi-scale wear mechanism of material surface and hinge interface based on TC4 alloy in space environment

Multi-scale wear mechanism of material surface and hinge interface based on TC4 alloy in space environment

Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR

Effect of Impact Velocity and Angle on Impact Wear Behavior of Zr-4 Alloy Cladding Tube

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