TEM/STEM study of Zircaloy-2 with protective FeAl(Cr) layers under simulated BWR environment and high-temperature steam exposure

Donghee Park, Peter A. Mouche, Weicheng Zhong, Kiran K. Mandapaka, Gary S. Was, Brent J. Heuser

Research output: Contribution to journalArticlepeer-review

17 Scopus citations

Abstract

FeAl(Cr) thin-film depositions on Zircaloy-2 were studied using transmission electron microscopy (TEM) and scanning transmission electron microscopy (STEM) with respect to oxidation behavior under simulated boiling water reactor (BWR) conditions and high-temperature steam. Columnar grains of FeAl with Cr in solid solution were formed on Zircaloy-2 coupons using magnetron sputtering. NiFe2O4 precipitates on the surface of the FeAl(Cr) coatings were observed after the sample was exposed to the simulated BWR environment. High-temperature steam exposure resulted in grain growth and consumption of the FeAl(Cr) layer, but no delamination at the interface. Outward Al diffusion from the FeAl(Cr) layer occurred during high-temperature steam exposure (700 °C for 3.6 h) to form a 100-nm-thick alumina oxide layer, which was effective in mitigating oxidation of the Zircaloy-2 coupons. Zr intermetallic precipitates formed near the FeAl(Cr) layer due to the inward diffusion of Fe and Al. The counterflow of vacancies in response to the Al and Fe diffusion led to porosity within the FeAl(Cr) layer.

Original languageEnglish
Pages (from-to)95-105
Number of pages11
JournalJournal of Nuclear Materials
Volume502
DOIs
StatePublished - Apr 15 2018
Externally publishedYes

Funding

This work was performed with support from the US Department of Energy Nuclear Energy University Programs Integrated Research Project under contract number IRP-12-4728 ( DE-00131989 ). In addition, this work was carried out in part in the Frederick Seitz Materials Research Laboratory Central Facilities, University of Illinois, which are partially supported by the US Department of Energy under Grants DE-FG02-07ER46453 and DE-FG02-07ER46471 .

FundersFunder number
US Department of Energy Nuclear Energy University Programs Integrated Research ProjectIRP-12-4728, DE-00131989
U.S. Department of EnergyDE-FG02-07ER46453, DE-FG02-07ER46471

    Keywords

    • Corrosion
    • FeCrAl
    • LWR cladding
    • Oxidation
    • Protective coatings
    • TEM

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