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

. Guerain M., Duriez C., Grosseau-Poussard J.L., Mermoux M., Review of stress fields in zirconium alloys corrosion scales. Corr. Sci. 95 (2015) 11–21. 36. Baris S., Abolhassani Y.L., Chiu L., Evans H.E., (2018) Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB Tomography – case of Zr-ZrO 2 in reactor. Mater. High Temp. 35 (2018) 14–21. 37. Birchley J., Fernandez-Moguel L. : Simulation of air oxidation during a reactor accident sequence: Part 1 - Phenomenology and model development. Ann. Nucl. Energy

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Hydrogen degradation of pre-oxidized zirconium alloys

oxidation during a reactor accident sequence: Part 1 - Phenomenology and model development. Ann Nucl Energy 2012;40:163-70. 11. Hózer Z., Győri C., Matus L., Horvàth M., Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings. J Nucl Mater 2008;373:415-23. 12. Elmoselhi M. B., Hydrogen uptake by oxidized zirconium alloys. J Alloys Comp 1995;231:716-21. 13. Steinbrück M., Birchley J., Boldyrev A. V., Goryachev A. V., Grosse M., Haste T. J., et al., Hightemperature oxidation and quench behaviour of Zircaloy-4

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