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

Bell, SB, Graening, T, Evans, A, Kelly, P ORCID: 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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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.

Item Type:	Article
Peer-reviewed:	Yes
Date Deposited:	28 Mar 2022 09:03
Publisher:	Elsevier
Additional Information:	This is an Author Accepted Manuscript of an article published in the Journal of Nuclear Materials by Elsevier.
Divisions:	Faculties > Science and Engineering
Subject terms:	0912 Materials Engineering, Energy
Report number:	153679
URI:	https://e-space.mmu.ac.uk/id/eprint/629407
DOI:	https://doi.org/10.1016/j.jnucmat.2022.153679
ISSN	0022-3115

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