journal article·2014-09

The mechanism and kinetics of the fuel cladding failure during loading after high-temperature oxidation

S.A. Nikulin, S.O. Rogachev, A.B. Rozhnov, A.Yu. Gusev, A.G. Malgin, N.N. Abramov, K.S. Zharovtseva, V.M. Khatkevich, M.V. Koteneva, E.V. Li

Journal of Nuclear Materials· Volume 452· Issue 1-3
Publisher page

Abstract

Abstract Complex analysis of the acoustic emission (AE), load–strain diagrams and step-by-step metallographic analysis have been used to examine the sequence of damage accumulation under loading in tubular E110 zirconium alloy specimens, which were subjected to high-temperature oxidation ( T = 1100 °C, ECR = 10%). The ECR value was determined by weight gain measurements. The fracture of samples under loading begins with the formation of brittle microcracks 30–50 μm long in the α-layer. Further, the cracks propagate simultaneously into oxide and “prior β”-layer until the formation of a through-wall crack.
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Research context

OpenAlex topics: Nuclear Materials and Properties · High Temperature Alloys and Creep · Nuclear reactor physics and engineering

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