Some observations on Zr-O solid solutions with a microprobe and by electron microscopy

Ericsson, Torsten; Östberg, Gustaf; Lehtinen, B.

doi:10.1016/0022-3115(68)90177-3

Cited by 31 publications

(16 citation statements)

References 5 publications

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“…7, and which are shoulders on the low two-theta side of alpha-Zr metal peaks). This phase has also been seen at the oxide-metal interface by various researchers in oxides formed in Zr alloys at low temperature [15][16][17][18][19][20].…”

Section: Microbeam Synchrotron Radiation Diffractionmentioning

confidence: 96%

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Motta

Yilmazbayhan

Silva

et al. 2007

Journal of Nuclear Materials

145

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Section: Microbeam Synchrotron Radiation Diffractionmentioning

confidence: 96%

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Motta

Yilmazbayhan

Silva

et al. 2007

Journal of Nuclear Materials

145

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“…To understand the migration mechanisms of hydrogen in zirconium suboxides, migration barriers for oxygen and hydrogen in interstitial solid solutions were calculated using the nudged elastic band approach [83]. It was established that, unlike in pure Zr, inside the zirconium suboxide lattice the migration barrier for moving oxygen atom from one octahedral interstitial to another is very high (>2 eV).…”

Section: Interstitial Oxygen and Hydrogen Solid Solutionsmentioning

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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“…The same difficulties were met by other authors (29) who estimated the oxygen content by substracting the zirconium content that they had measured. The absorption coefficients for oxygen are not known well enough to permit an improvement of those results.…”

Section: Resultsmentioning

confidence: 85%

“…At first sight, there is no reason why microhardness should vary linearly with concentration; some authors (16) have however tried to measure the gradient by relying on preceeding but imprecise correlating measurements. 7), (16,26,27,29,30). Moreover, plateaus appear in the microhardness curve as the oxidation time is increased and so the results are made more difficult to use ( fig.…”

Section: Resultsmentioning

confidence: 99%

Does the Oxidation of Zirconium obey Wagner's Theory??

Lacombe

Béranger

Boisot

et al. 1970

Materials & Corrosion

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The use of different experimental analysis methods allowed to evidence a rigorously parabolic law for oxidation of zirconium after an initially disturbed period which has been related to the oxide layer formation. The oxygen dissolution in the metal follows a parabolic law right from its start. Wagner's theory relative to diffusion in an homogeneous phase with formation of an oxide layer is in good agreement with the kinetic results. However, this theory should be adapted to take into account the different atomic scale phenomena and especially the oxygen diffusion in zirconium.

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Some observations on Zr-O solid solutions with a microprobe and by electron microscopy

Cited by 31 publications

References 5 publications

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

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

Does the Oxidation of Zirconium obey Wagner's Theory??

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