3D visualisation of crack distributions in oxidised zirconium alloys by FIB-slicing

Zirconium alloys have been used as fuel cladding and structural fuel assembly components in nuclear reactors since the 1950s, and show a characteristic variation in oxidation rate and layered crack morphology during aqueous corrosion. It is common to associate the first phenomenon with the appearanc...

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Những tác giả chính: Grovenor, C, Ni, N, Yardley, S, Hughes, G, Lozano-Perez, S, Sykes, J
Định dạng: Journal article
Ngôn ngữ:English
Được phát hành: 2012
Miêu tả
Tóm tắt:Zirconium alloys have been used as fuel cladding and structural fuel assembly components in nuclear reactors since the 1950s, and show a characteristic variation in oxidation rate and layered crack morphology during aqueous corrosion. It is common to associate the first phenomenon with the appearance of the second. We have used 3D serial sectioning to study the morphology and distribution of cracks in corroded ZIRLO samples at different stages of oxidation, and have shown that cracks nucleate and grow at all stages of the oxidation process not just at the kinetic transition. We have used this data to analyse the nucleation of cracks with reference to the shape of the oxide/metal interface and the distribution of second phase precipitates. © 2012 Materials Research Society.