Strain evolution during hydride precipitation in Zircaloy-4 observed with synchrotron X-ray diffraction

Blackmur, Matthew S.; Preuß, Michael; Robson, James; Zanellato, Olivier; Cernik, Robert J.; Ribeiro, Fabienne; Andrieux, J.

doi:10.1016/j.jnucmat.2016.01.039

Cited by 25 publications

(11 citation statements)

References 80 publications

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“…The resulting stress component values are shown in Table 2. These should be taken as crude estimates, given that ζ 11 and ζ 22 vary considerably over the length of the disc shaped hydride. It should also be recognized that the stress components listed in Table 2 generate equivalent stresses that obey the assumed hydride yield stress at the appropriate temperature [45].…”

Section: An Explanation For the δ-Hydride D-spacing Behavior During Tmentioning

confidence: 99%

“…While recent studies have utilized high-energy synchrotron radiation to examine the hydride dissolution/precipitation behavior in situ during thermal cycling behavior of Zircaloy-4 [6][7][8][9][10][11][12], several aspects of the observed behavior of the d-spacing of hydride planes during thermomechancial cycling are yet to be fully understood. For example, the observation of thermal contraction of the hydride d-spacing during heating as hydrides dissolve remains unexplained [8].…”

Section: Introductionmentioning

confidence: 99%

“…. , where d face is δ{111} d-spacing of planes aligned with the platelet face (the ζ 22 direction) and d edge is the corresponding d-spacing of planes aligned with the platelet edges (the ζ11 and ζ 33 directions), and d =(d face +d edge )/2. The average values of ζ 11 = ζ 33 were obtained from ζ 11 = (3ζ m -ζ 22 )/2, where the ζ m -and ζ 22 -values are from Figs.…”

mentioning

confidence: 99%

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In situ synchrotron X-ray diffraction study of hydrides in Zircaloy-4 during thermomechanical cycling

Cinbiz

Koss

Motta

et al. 2017

Journal of Nuclear Materials

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The d-spacing evolution of both in-plane and out-of-plane hydrides has been studied using in situ synchrotron radiation X-ray diffraction during thermo-mechanical cycling of cold-worked stress-relieved Zircaloy-4. The structure of the hydride precipitates is such that the δ{111} d-spacing of the planes aligned with the hydride platelet face is greater than the d-spacing of the 111 planes aligned with the platelet edges. Upon heating from room temperature, the δ{111} planes aligned with hydride plate edges exhibit bi-linear thermally-induced expansion. In contrast, the d-spacing of the (111) plane aligned with the hydride plate face initially contracts upon heating. These experimental results can be understood in terms of a reversal of stress state associated with precipitating or dissolving hydride platelets within the αzirconium matrix.

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Section: An Explanation For the δ-Hydride D-spacing Behavior During Tmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

mentioning

confidence: 99%

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In situ synchrotron X-ray diffraction study of hydrides in Zircaloy-4 during thermomechanical cycling

Cinbiz

Koss

Motta

et al. 2017

Journal of Nuclear Materials

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“…In this sense, our results do not include important features of the Zr hydride particles such as their elongated shape and/or their orientation. Excellent recent examples of experimental characterization displaying all of these structure complexities exist now in the literature [99][100][101]. They can act, however, as a good springboard from which to connect to other methods such as phase field simulations [27,102,103], or orientation-dependent precipitation models [104,105].…”

Section: Discussionmentioning

confidence: 99%

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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“…This will allow its performance in reactor, in storage and in disposal conditions to be better understood and predicted [10,11].…”

Section: Developments In Fuel Technologymentioning

confidence: 99%

Challenges to deployment of twenty-first century nuclear reactor systems

Ion¹

2017

Proc. R. Soc. A.

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The science and engineering of materials have always been fundamental to the success of nuclear power to date. They are also the key to the successful deployment and operation of a new generation of nuclear reactor systems and their associated fuel cycles. This article reflects on some of the historical issues, the challenges still prevalent today and the requirement for significant ongoing materials R&D and discusses the potential role of small modular reactors.

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Strain evolution during hydride precipitation in Zircaloy-4 observed with synchrotron X-ray diffraction

Cited by 25 publications

References 80 publications

In situ synchrotron X-ray diffraction study of hydrides in Zircaloy-4 during thermomechanical cycling

In situ synchrotron X-ray diffraction study of hydrides in Zircaloy-4 during thermomechanical cycling

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

Challenges to deployment of twenty-first century nuclear reactor systems

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