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Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing

Bell, SB, Graening, T, Evans, A, Kelly, P ORCID logoORCID: https://orcid.org/0000-0003-1008-4941, Pint, BA and Kane, KA (2022) Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing. Journal of Nuclear Materials, 564. p. 153679. ISSN 0022-3115

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File will be available on: 19 March 2023.
Available under License Creative Commons Attribution Non-commercial No Derivatives.

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Abstract

Cr-coated Zr-alloys are a near-term cladding concept to improve reactor safety during accident scenarios. Burst and steam oxidation behavior of bare and Cr-coated Zirlo claddings were examined under simulated loss-of-coolant accident conditions. The 4.4 µm coating had no substantial effect on ballooning or opening geometry but did increase burst temperatures at higher pressures. The coating reduced steam oxidation of the cladding compared to bare specimens, but in regions of high strain, the coating developed through-cracks allowing rapid underlying zirconia formation.

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