Hydrogen in zirconium alloys: A review

Motta, Arthur T.; Capolungo, Laurent; Chen, Lei; Cinbiz, Mahmut Nedim; Daymond, Mark R.; Koss, D. A.; Lacroix, Evrard; Pastore, Giovanni; Simon, Pierre; Tonks, Michael; Wirth, Brian D.; Zikry, M. A.

doi:10.1016/j.jnucmat.2019.02.042

Cited by 262 publications

(106 citation statements)

References 96 publications

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“…Figure 5 shows the buildup of hydrogen up to the first 580 h. This represents a dynamic Dirichlet boundary condition for the spatially-resolved SCD calculations of hydride nucleation and growth in the metal substrate (g term in Equation (12)). Second, we track the sampling rate r i defined in Section 2.3.5 to confirm that it matches Equation (18). Figure 6 shows a comparison between both, indeed demonstrating their equivalency and confirming the correctness of its implementation in the code.…”

Section: Resultsmentioning

confidence: 61%

“…This is added to the event catalog and sampled with the corresponding probability as given by Equation (18). As the equation shows, this is a time-dependent rate that reflects the nonlinear growth of the oxide layer with time.…”

Section: Metal/oxide Interface Motionmentioning

confidence: 99%

“…In principle, Zr clad is subjected to corrosion from the coolant (water) and fuel sides, both by way of oxygen and hydrogen penetration. The oxidation and hydrogenation of zirconium fuel components in LWR may affect reactor safety and efficiency, which makes corrosion a critical design aspect of Zr materials response in nuclear environments [12][13][14][15][16][17][18].…”

Section: Introductionmentioning

confidence: 99%

“…at 810 K [21]. Although δ Zr 2 H 3 displays good thermo-mechanical stability, it is also an exceedingly brittle phase [28][29][30][31] that can compromise the clad's mechanical integrity [18,[31][32][33].…”

Section: Introductionmentioning

confidence: 99%

“…Comparison between the predictions of r i and Equation(18) of the position of the oxide/metal interface as a function of time. We track the interface position only after the concentration of hydrogen has reached the solubility limit.…”

mentioning

confidence: 99%

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Kinetic Model of Incipient Hydride Formation in Zr Clad under Dynamic Oxide Growth Conditions

Reyes

Shah

et al. 2020

Materials

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The formation of elongated zirconium hydride platelets during corrosion of nuclear fuel clad is linked to its premature failure due to embrittlement and delayed hydride cracking. Despite their importance, however, most existing models of hydride nucleation and growth in Zr alloys are phenomenological and lack sufficient physical detail to become predictive under the variety of conditions found in nuclear reactors during operation. Moreover, most models ignore the dynamic nature of clad oxidation, which requires that hydrogen transport and precipitation be considered in a scenario where the oxide layer is continuously growing at the expense of the metal substrate. In this paper, we perform simulations of hydride formation in Zr clads with a moving oxide/metal boundary using a stochastic kinetic diffusion/reaction model parameterized with state-of-the-art defect and solute energetics. Our model uses the solutions of the hydrogen diffusion problem across an increasingly-coarse oxide layer to define boundary conditions for the kinetic simulations of hydrogen penetration, precipitation, and dissolution in the metal clad. Our method captures the spatial dependence of the problem by discretizing all spatial derivatives using a stochastic finite difference scheme. Our results include hydride number densities and size distributions along the radial coordinate of the clad for the first 1.6 h of evolution, providing a quantitative picture of hydride incipient nucleation and growth under clad service conditions.

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Section: Resultsmentioning

confidence: 61%

Section: Metal/oxide Interface Motionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

mentioning

confidence: 99%

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Kinetic Model of Incipient Hydride Formation in Zr Clad under Dynamic Oxide Growth Conditions

Reyes

Shah

et al. 2020

Materials

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Dislocation‐Mediated Hydride Precipitation in Zirconium

Liu

Ishii

et al. 2021

Small

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The formation of hydrides challenges the integrity of zirconium (Zr) fuel cladding in nuclear reactors. The dynamics of hydride precipitation are complex. Especially, the formation of the butterfly or bird‐nest configurations of dislocation structures around hydride is rather intriguing. By in‐situ transmission electron microscopy experiments and density functional theory simulations, it is discovered that hydride growth is a hybrid displacive‐diffusive process, which is regulated by intermittent dislocation emissions. A strong tensile stress field around the hydride tip increases the solubility of hydrogen in Zr matrix, which prevents hydride growth. Punching‐out dislocations reduces the tensile stress surrounding the hydride, decreases hydrogen solubility, reboots the hydride precipitation and accelerates the growth of the hydride. The emission of dislocations mediates hydride growth, and finally, the consecutively emitted dislocations evolve into a butterfly or bird‐nest configuration around the hydride.

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