A unified model of Zircaloy BWR corrosion and hydriding mechanisms

Rudling, Peter; Wikmark, Gunnar

doi:10.1016/s0022-3115(98)00613-8

Cited by 75 publications

(30 citation statements)

References 30 publications

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“…Concerning oxygen diffusion via grain boundaries, differences of several orders of magnitude between grain boundary conductivity and the conductivity inside the grains have been reported (grain boundary diffusion >> diffusion via/in grains) [70]. For oxide scales grown on Zr-based alloys at temperatures around 400°C, two crystallographic phases of zirconia have been reported: monoclinic and tetragonal.…”

Section: Oxidationmentioning

confidence: 99%

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: Oxidationmentioning

confidence: 99%

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

Glazoff¹

2013

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“…The corrosion behaviour of Zr-based materials has been extensively studied during the last decade with a wide variety of techniques [1][2][3][4][5][6][7][8][9][10]. The role of a surface oxide layer is to protect the metal substrate against the corrosive environment.…”

Section: Introductionmentioning

confidence: 99%

“…The distribution of ZrO 2 phases in the oxide layer is also changing in depth. Tetragonal and monoclinic ZrO 2 phases have been reported [3,6,8,12]. The fraction of tetragonal phase is higher at the oxide/metal, O/M, interface (stabilized by high compressive stress) and is irregularly distributed in the oxide [3].…”

Section: Introductionmentioning

confidence: 99%

“…Tetragonal and monoclinic ZrO 2 phases have been reported [3,6,8,12]. The fraction of tetragonal phase is higher at the oxide/metal, O/M, interface (stabilized by high compressive stress) and is irregularly distributed in the oxide [3]. The tetragonal to monoclinic phase transformation takes place as a result of stress relief with a volume expansion of 7% and generates defects like cracks and pores (easy diffusion pathways) [3].…”

Section: Introductionmentioning

confidence: 99%

“…The fraction of tetragonal phase is higher at the oxide/metal, O/M, interface (stabilized by high compressive stress) and is irregularly distributed in the oxide [3]. The tetragonal to monoclinic phase transformation takes place as a result of stress relief with a volume expansion of 7% and generates defects like cracks and pores (easy diffusion pathways) [3]. This transformation can occur inside the barrier layer, possibly inducing porosity within the 0022-3115/$ -see front matter Ó 2005 Elsevier B.V. All rights reserved.…”

Section: Introductionmentioning

confidence: 99%

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