Journal article
Determination of the initial oxidation behavior of Zircaloy-4 by in-situ TEM
Journal of nuclear materials, v 474(C), pp 126-133
01 Jun 2016
Featured in Collection : UN Sustainable Development Goals @ Drexel
Abstract
The corrosion behavior of Zircaloy-4 (Zry-4), specifically by oxidation, is a problem of great importance as this material is critical for current nuclear reactor cladding. The early formation behavior and structure of the oxide layer during oxidation was studied using in-situ TEM techniques that allowed for Zry-4 to be monitored during corrosion. These environmental exposure experiments were coupled with precession electron diffraction to identify and quantify the phases present in the samples before and after the oxidation. Following short-term, high temperature oxidation, the dominant phase was revealed to be monoclinic ZrO2 in a columnar structure. These samples oxidized in-situ contained structures that correlated well with bulk Zry-4 subjected to autoclave treatment, which were used for comparison and validation of this technique. By using in-situ TEM the effect of microstructure features, such as grain boundaries, on oxidation behavior of an alloy can be studied. The technique presented herein holds the potential to be applied any alloy system to study these effects. (C) 2016 Elsevier B.V. All rights reserved.
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Details
- Title
- Determination of the initial oxidation behavior of Zircaloy-4 by in-situ TEM
- Creators
- Wayne Harlow - Drexel UniversityHessam Ghassemi - Drexel UniversityMitra L. Taheri - Drexel University
- Publication Details
- Journal of nuclear materials, v 474(C), pp 126-133
- Publisher
- Elsevier
- Number of pages
- 8
- Grant note
- DE-AC07-05I-D14517 / DOE Office of Nuclear Energy's Nuclear Energy University Programs; United States Department of Energy (DOE) DE-SC0008274 / United States Energy Basic Energy Sciences Early Career Program
- Resource Type
- Journal article
- Language
- English
- Web of Science ID
- WOS:000374870100015
- Scopus ID
- 2-s2.0-84962179505
- Other Identifier
- 991019330914404721
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InCites Highlights
Data related to this publication, from InCites Benchmarking & Analytics tool:
- Web of Science research areas
- Materials Science, Multidisciplinary
- Nuclear Science & Technology