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X-ray computer tomography study of degradation of the zirvaloy-2 tubes oxidized at high temperatures

Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
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.
Rocznik
Strony
54--71
Opis fizyczny
Bibliogr. 42 poz., rys.
Twórcy
autor
  • Gdansk University of Technology, Faculty of Mechanical Engineering, Department of Materials Science and Welding Engineering, Narutowicza 11/12, 80-233 Gdańsk, Poland
autor
  • C.N.R.S., I2M, UMR 5295, 351 cours de la Liberation, Talence 33405, France
autor
  • PLACAMAT : Plateforme Aquitaine de Caractérisation des Matériaux: UMS C.N.R.S. 3626, 87 Av. Du Dr. A. Schweitzer, 33600 Pessac, France
  • Gdansk University of Technology, Faculty of Mechanical Engineering, Department of Materials Science and Welding Engineering, Narutowicza 11/12, 80-233 Gdańsk, Poland
Bibliografia
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  • 9. Harlow W., Ghassemi H., Taheri M.L., Determination of the initial oxidation behavior of Zircaloy-4 by in-situ TEM. J. Nucl. Mater. 474 (2016) 126-133.
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  • 20. Park D.J., Park J.Y., Jeong J.H., Microstructural analysis and XPS investigation of nodular oxides formed on Zircaloy-4. J. Nucl. Mater. 412 (2011) 233-238.
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  • 23. Ni N., Lozano-Perez S., Sykes J.M., Smith G.D.W., Grovenor C.R.M., Focussed ion beam sectioning for the 3D characterisation of cracking in oxide scales formed on commercial ZIRLO™ alloys during corrosion in high temperature pressurised water. Corr. Sci. 53 (2011) 4073-4083.
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  • 40. Steinbrück M., Birchley J., Boldyrev A.V., Goryachev A.V., Grosse M., Haste T.J., Hózer Z., Kisselev A.E., Nalivaev V.I., Semishkin V.P., Sepold L., Stuckert J., Vér N., Veshchunov M.S., High temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys. Progr. Nucl. Energy 52 (2010) 19-36.
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Uwagi
PL
Opracowanie rekordu w ramach umowy 509/P-DUN/2018 ze środków MNiSW przeznaczonych na działalność upowszechniającą naukę (2019).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-13beb958-9cd7-4294-8edc-e342b5fe0ff4
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