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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: Eleventh International Symposium
By
ER Bradley
ER Bradley
1
Sandvik Special Metals Corporation
,
Kennewick, Washington
;
symposium chairman and STP editor
Search for other works by this author on:
GP Sabol
GP Sabol
2
Westinghouse Electric Corporation
,
Pittsburgh, Pennsylvania
;
editorial chairman and STP editor
Search for other works by this author on:
ISBN-10:
0-8031-2406-6
ISBN:
978-0-8031-2406-6
No. of Pages:
921
Publisher:
ASTM International
Publication date:
1996

In-pile grown corrosion films on different fuel rod claddings (standard Zircaloy-4, extra low tin Zircaloy (ELS), and Zr2.5Nb) have been studied using a variety of experimental techniques. The aim of the investigations was to find out common features and differences between the corrosion layers grown on zirconium alloys having different composition. Methods applied were scanning and transmission electron microscopy (SEM, TEM), electrochemical impedance spectroscopy (EIS), and electrochemical anodization. The morphology and topography of these oxide layers are, in general, of common nature. However, morphological differences have been observed between the specimens that could explain the irradiation enhancement of corrosion of Zircaloy-4. The features of the compact oxide close to the oxide/metal interface have been characterized by electrochemical methods. The relationship between the thickness of this protective oxide and the overall oxide thickness has been investigated by EIS. It was found that this relation is dependent on the location of the oxide along the fuel rod and on the corrosion rate.

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,
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,
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19.
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, ASTM STP 1245,
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, ASTM STP 1245,
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,”
Surface and Interface Analysis
, in press.
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