Abstract
Methods of study and criteria of evaluation of stress corrosion cracking (SCC) of zirconium alloys are generalized as applied to cladding tubes of nuclear reactors. Mechanisms of SCC in zirconium cladding tubes in iodine-bearing media (iodine vapors, solution of iodine in methanol, etc.) are described. Metallographic and fracture features of damage in these media are analyzed. Data on cracking rates and critical stress intensity factors are presented.
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