Transmission electron microscopy examination of oxide layers formed on Zr alloys

Yilmazbayhan, Aylin; Breval, E.; Motta, Arthur T.; Comstock, R. J.

doi:10.1016/j.jnucmat.2005.10.012

Cited by 251 publications

(164 citation statements)

References 10 publications

(26 reference statements)

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“…This phase has also been seen at the oxide-metal interface by various researchers in oxides formed in Zr alloys at low temperature [77][78][79][80][81][82]. In particular, the diffraction pattern from synchrotron radiation shows strong Zr 3 O peaks in a two to three micron region next to the oxide-metal interface corrosion.…”

Section: Suboxides Of Zirconiummentioning

confidence: 53%

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Glazoff¹

2013

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Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel.This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.

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Section: Suboxides Of Zirconiummentioning

confidence: 53%

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Glazoff¹

2013

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“…As a matter of fact, the tetragonal layer has probably a crystallographic texture as mentioned in papers [2,5], but the anisotropy of the tetragonal phase is low and a crystallographic texture does not induce a large modification of the properties of the layer.…”

Section: Figmentioning

confidence: 97%

“…The Voigt solution (i.e. the strain is uniform over the RVE) leads to the result: < σ xx > g = C 11 xg ε 0 and is represented by a straight Zirconia layer presents a crystallographic texture [2,4,9]; Parise et al [9] found a fiber texture with the c axis of the monoclinic unit cell parallel to the z axis, that is normal to the metal-oxide interface. So, this fiber texture must be taken into account in the aggregate modeling: the crystalline orientation of each grain is defined by one angle around the c axis.…”

Section: Figmentioning

confidence: 99%

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Microstresses in ZrO<sub>2</sub> Layer and Lateral Cracking

Berdin

Tang

Pascal

2014

AMR

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Abstract. Micromechanical simulations of polycrystalline zirconia using the finite element method are performed in order to obtain the stresses at the grain scale of a zirconium oxide layer, since these microstresses are important for damage prediction of the layer and then oxidation kinetics. The crystallographic texture of the layer of monoclinic zirconia is taken into account. The results show that even under high compressive macroscopic stresses, the microstresses can contribute to lateral cracking promoted by the presence of tetragonal zirconia.

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“…In engineering ceramics this mechanism is referred to as transformation toughening because of the resulting retardation of crack growth by the tetragonal to monoclinic phase change and its associated increase in volume (Budiansky, 1983;Evans and Heuer, 1980;Kelly and Francis Rose, 2002). Oxides formed on zirconium alloys in autoclave and reactor undergo a transition and acceleration in the corrosion kinetics that has previously been linked with the formation of a network of lateral cracks close to the metal-oxide interface (Bossis et al, 2001;Polatidis et al, 2013;Yilmazbayhan et al, 2006).…”

Section: Introductionmentioning

confidence: 99%

Peridynamic simulations of the tetragonal to monoclinic phase transformation in zirconium dioxide

Platt

Mella

DeMaio

et al. 2017

Computational Materials Science

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Whether present as a manufactured stabilised ceramic, or as an oxide layer on zirconium alloys, mechanical degradation in zirconia is influenced by the tetragonal to monoclinic phase transformation.Peridynamic theory was implemented within the Abaqus finite element framework to understand how the tetragonal to monoclinic phase transformation can itself cause fracture in zirconia. In 2D these simulations represent a single grain, transforming via an isometric dilational expansion, surrounded by a homogenous monoclinic oxide. The effect of transformation time, applied bi-axial pressure, and the fracture strain were assessed using the change in strain energy and the amount of damage in the oxide surrounding the transformed grain. Reducing the applied compressive stress or applying a tensile stress reduces the transformation strain energy. The introduction of a fracture strain leads to damage in the surrounding oxide region largely in the form of cracks, and reduces the transformation strain energy further by reducing the constraint on the transforming grain. The extent of the fracture, and reduction in constraint on the transformed grain, is more significant with the application of a biaxial tensile pressure.

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Transmission electron microscopy examination of oxide layers formed on Zr alloys

Cited by 251 publications

References 10 publications

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Microstresses in ZrO<sub>2</sub> Layer and Lateral Cracking

Peridynamic simulations of the tetragonal to monoclinic phase transformation in zirconium dioxide

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