作者: R. A. Antunes , M. C. Lopes de Oliveira , J. A. Batista de Souza
DOI: 10.1179/1743278215Y.0000000036
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摘要: Nuclear fuel cladding for pressurised water reactors is commonly manufactured with zirconium alloys. The M5 alloy a relatively new material in-reactor used enhanced performance compared to traditional zircaloys. In this work, the influence of temperature on corrosion resistance and semiconducting properties passive film formed in borate buffer solution has been evaluated. electrochemical behaviour was assessed by potentiodynamic polarisation tests, impedance spectroscopy Mott–Schottky plots. results indicated that decreased due formation less stable more defective film. approach combination tests measurements effective reveal protective state alloy.