High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding

Lee, Cheol Min; Mok, Yong-Kyoon; Sohn, Dong-Seong

doi:10.1016/j.jnucmat.2017.10.013

Cited by 30 publications

(2 citation statements)

References 27 publications

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“…The rapid transformation of tetragonal oxide to monoclinic oxide is likely the main reason for the appearance of poor-quality monoclinic oxide [3]. The circumferential cracks at the oxide/metal interface decrease the oxidation rate by limiting the oxygen diffusion before the breakaway oxidation start [21]. For the E110 alloy, the fracture started with the formation of brittle cracks 30-50 µm long in the α-layer, which then propagated simultaneously into the oxide and prior β-layers [22].…”

Section: Introductionmentioning

confidence: 99%

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

Trybuś

Olivé

Lenoir

et al. 2019

Advances in Materials Science

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The investigations of high-temperature oxidation of zirconium alloys, applied for fuel pellets in nuclear power plants, are usually limited to oxidation kinetics, phase transformations and microstructural characterization. The purpose of this research was to characterize the degradation phenomena occurring within oxide layer and at the interface oxide/metal, on internal and external Zircaloy-2 tube surfaces, below and over crystalline transformation temperature of zirconium oxides. The commercial tubes were oxidized at 1273 K and 1373 K in calm air for 30 min and then examined with a technique novel for such purpose, namely a high-resolution X-ray computer tomography. The light microscopy was used to examine the cross-surfaces. The obtained results show that the form and intensity of oxide damage is significant and it is in a complicated way related to oxidation temperature and on whether external or internal tube surface is studied. The found oxide layer damage forms include surface cracks, the detachment of oxide layers, the appearance of voids, and nodular corrosion. The oxidation effects and damage appearance are discussed taking into account the processes such as formation of oxides, their phase transformation, stress-enhanced formation and propagation of cracks, diffusion of vacancies, formation of nitrides, diffusion of hydrogen into interface oxide-metal, incubation of cracks on second phase precipitates are taken into account to explain the observed phenomena.

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Section: Introductionmentioning

confidence: 99%

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

Trybuś

Olivé

Lenoir

et al. 2019

Advances in Materials Science

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“…Zirconium-based alloys are widely used as the main structural material in nuclear reactors due to low thermal neutron cross-section, high melting point, high corrosion resistance in water at 280-350 • C and acceptable mechanical properties. The operation experience of nuclear reactors showed that zirconium alloys are subjected to corrosion and hydrogen embrittlement [1,2]. Hydrogen is generated during water radiolysis and corrosion reaction between zirconium and water under reactor operation.…”

Section: Introductionmentioning

confidence: 99%

Hydrogen Interaction with Deep Surface Modified Zr-1Nb Alloy by High Intensity Ti Ion Implantation

Kashkarov

Ryabchikov

Kurochkin

et al. 2018

Metals

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A deep surface modified TiZr layer was fabricated by high-intensity low-energy titanium ion implantation into zirconium alloy Zr-1Nb. Gas-phase hydrogenation was performed to evaluate protective properties of the modified layer against hydrogen permeation into Zr-1Nb alloy. The effects of ion implantation and hydrogen on microstructure, phase composition and elemental distribution of TiZr layer were analyzed by scanning electron microscopy, X-ray diffraction, and glow-discharge optical emission spectroscopy, respectively. It was revealed that TiZr layer (~10 μm thickness) is represented by α′ + α(TiZr) lamellar microstructure with gradient distribution of Ti through the layer depth. It was shown that the formation of TiZr layer provides significant reduction of hydrogen uptake by zirconium alloy at 400 and 500 °C. Hydrogenation of the modified layer leads to refinement of lamellar plates and formation of more homogenous microstructure. Hydrogen desorption from Ti-implanted Zr-1Nb alloy was analyzed by thermal desorption spectroscopy. Hydrogen interaction with the surface modified TiZr layer, as well as its resistance properties, are discussed.

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The Influence of Specimen Surface Roughness and Temperature of Steam Injection on Breakaway Oxidation Behavior of Zry-4 Fuel Cladding in Steam at 1273 K

Negyesi

Amaya

2020

Oxid Met

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High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding

Cited by 30 publications

References 27 publications

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

Hydrogen Interaction with Deep Surface Modified Zr-1Nb Alloy by High Intensity Ti Ion Implantation

The Influence of Specimen Surface Roughness and Temperature of Steam Injection on Breakaway Oxidation Behavior of Zry-4 Fuel Cladding in Steam at 1273 K

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