3D simulation of hydride-assisted crack propagation in zircaloy-4 using XFEM

Suman, Siddharth; Khan, Mohd. Kaleem; Pathak, Manabendra; Singh, R.N.

doi:10.1016/j.ijhydene.2017.04.163

Cited by 26 publications

(6 citation statements)

References 18 publications

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“…Figure shows the increase in stress intensity factors and J‐integrals for different crack lengths due to precipitation of hydride. Evidently, it would enhance the propagation of crack in Zircaloy‐4 . Another interesting observation is that severity induced due to the presence of a hydride increases with increase in the crack length.…”

Section: Resultsmentioning

confidence: 96%

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Effects of δ-hydride precipitated at a crack tip on crack instability in Zircaloy-4

et al. 2017

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Summary A fraction of hydrogen produced due to the waterside corrosion of Zircaloy‐4 nuclear fuel cladding diffuses into it. Diffused hydrogen migrates up a stress gradient in the Zircaloy‐4 and accrues in the regions of higher stress like a crack tip. When the concentration of hydrogen exceeds terminal solid solubility, it precipitates as brittle hydride phases. Hydride precipitated at the tip of a crack may induce crack instability, causing failure of the cladding. To understand the effects of hydride precipitated at the tip of a crack on crack instability in Zircaloy‐4, a numerical investigation is performed on single‐edge notched tension specimen by using the extended finite element method. The mechanical properties of the Zircaloy‐4 cladding and hydride precipitated in it—used in this numerical analysis—are evaluated by using nanoindentation technique. The crack length is taken between 0.05 and 0.2 mm, while the length of the hydride is varied in the range of 0.1 to 0.2 mm. The influence of hydride dimensions, number of hydrides, orientation of hydrides, and distance of hydride from the crack tip on crack instability is evaluated. The stability of the crack is assessed in stress intensity factor and J‐integral for each case. Results reveal that stress distribution around the crack tip is significantly altered by the precipitation of hydride. The circumferential hydride is less detrimental compared with the radial hydride. As the distance of hydride from the crack tip increases, there is a decline in the stress intensity factors and J‐integrals, implicating that there may exist a critical distance beyond which hydride precipitation has negligible effect on crack instability.

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Section: Resultsmentioning

confidence: 96%

“…Evidently, it would enhance the propagation of crack in Zircaloy-4. 13,[25][26][27] Another interesting observation is that severity induced due to the presence of a hydride increases with increase in the crack length. The change in stress intensity factor due to precipitation of hydride is 39.27% for 0.05 mm crack, while it is 55.59%…”

Section: Resultsmentioning

confidence: 99%

Effects of δ-hydride precipitated at a crack tip on crack instability in Zircaloy-4

et al. 2017

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“…However, numerous models have been developed to study DHC in zirconium-based materials at different scales. It is worth to mention the model based on the extended finite element method developed by Suman et al [98,99] or the multi-physics modeling done by Xia et al [100]…”

Section: Delayed Hydride Crackingmentioning

confidence: 99%

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Konarski

Cozzo

Khvostov

et al. 2021

Journal of Nuclear Materials

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The role of dry storage in spent nuclear fuel management becomes more and more important. Originally intended to serve as a temporary solution for a few decades until final disposal, now dry storage period is to be extended to 100 years and beyond. It has to be proven for licensing that the fuel rod integrity during dry storage is ensured. Since it is difficult to provide experimental support, the licensing process has to rely largely on numerical simulations. This paper reviews the literature associated with the modeling of spent nuclear fuel under dry storage conditions. The main phenomena threatening the fuel rod integrity and the numerical models representing them are described here. Moreover, the most recent or currently ongoing experimental efforts that could support the modeling of nuclear fuel in dry storage in the future are discussed. Finally, this paper reviews approaches to dry storage modeling chosen by different countries. In general, these approaches are similar and can be described as a calculation chain consisting of neutronics-thermo-hydraulics-fuel performance computations where sensitivity and uncertainty studies are crucial elements.

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“…During the operation in water-cooled power reactors and pressurized water reactors (PWR) in zirconium fuel claddings, the gradient of hydrogen concentration through the cladding wall thickness and hydride initiation is formed, accompanied by hydride rim formation. Formation of the hydride layer with the thickness of 50-100 µm takes place on the outer surface of the fuel cladding; the hydride layer thickness depends on the degree of hydrogenation [14][15][16][17][18][19].…”

Section: Introductionmentioning

confidence: 99%

Hydride Rim Formation in E110 Zirconium Alloy during Gas-Phase Hydrogenation

Kudiiarov

Sakvin

Сыртанов

et al. 2020

Metals

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The work is devoted to the study of the laws of the formation of a hydride rim in E110 zirconium alloy claddings during gas-phase hydrogenation. The problem of hydrogen penetration and accumulation and the subsequent formation of hydrides in the volume of zirconium cladding tubes of water-cooled power reactors remain relevant. The formation of brittle hydrides in a zirconium matrix firstly, leads to a significant change in the mechanical properties, and secondly, can cause the destruction of the claddings by the mechanism of delayed hydride cracking. The degree of the hydride’s effect on the mechanical properties of zirconium cladding is mainly determined by the features of the hydride’s distribution and orientation. The problem of hydride rim formation in zirconium alloys with niobium is quite new and poorly studied. Therefore, the study of hydride rim formation in Russian zirconium alloy is important and necessary for predicting the behavior of claddings during the formation of the hydride rim.

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3D simulation of hydride-assisted crack propagation in zircaloy-4 using XFEM

Cited by 26 publications

References 18 publications

Effects of δ-hydride precipitated at a crack tip on crack instability in Zircaloy-4

Effects of δ-hydride precipitated at a crack tip on crack instability in Zircaloy-4

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Hydride Rim Formation in E110 Zirconium Alloy during Gas-Phase Hydrogenation

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