Fabrication, characterization, and testing of Cr-coated Zr alloy nuclear fuel rod cladding for enhanced accident tolerance

A. K. Evans, P. J. Kelly, D. T. Goddard, A. Cole-Baker, G. Obasi, M. Preuss, E. P. Vernon

Research output: Chapter in Book/Report/Conference proceedingConference PaperOther


The deposition of an oxidation resistant Cr coating onto a Zr alloy nuclear fuel cladding is a near term concept for the deployment of an accident tolerant fuel. In the UK, a collaborative programme of research is focused on the production of Cr coated Zr alloy fuel cladding material using magnetron sputtering, a coating technology which can be scaled up for industrial use. This research is investigating how the integrity and microstructure of the coating is affected by deposition conditions and coating thickness. The formation of a Cr-Zr liquid eutectic between 1280°C - 1380°C may limit the ultimate high temperature performance of the cladding and therefore the use of an interlayer has been investigated to limit any diffusion between the Cr coating and the Zr alloy. Test coatings have been subjected to accelerated autoclave tests in 400°C steam as well as high temperature (700-900°C) air oxidation. The deposited Cr coatings have exhibited excellent performance to date.

Original languageEnglish
Title of host publicationLight Water Reactor Fuel Performance Conference (TOP FUEL 2019)
PublisherAmerican Nuclear Society
Number of pages9
Publication statusPublished - 2020
Externally publishedYes
EventLight Water Reactor Fuel Performance Conference 2019 - Seattle, United States of America
Duration: 22 Sep 201927 Sep 2019
Conference number: 14th


ConferenceLight Water Reactor Fuel Performance Conference 2019
Abbreviated titleTOP FUEL 2019
Country/TerritoryUnited States of America
Internet address

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