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Microstructural Effects on the Scc Morphology of Alloy 600 in Deaerated Water

Published online by Cambridge University Press:  02 July 2020

M.G. Burke  and
D.M. Symons
M.G. Burke
Affiliation:
Bettis Atomic Power Laboratory, Westinghouse Electric Corp., West Mifflin, PA15122
D.M. Symons
Affiliation:
Bettis Atomic Power Laboratory, Westinghouse Electric Corp., West Mifflin, PA15122
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Extract

Previous studies on the stress corrosion cracking (SCC) behavior of Alloy 600 forgings revealed a correlation between the SCC susceptibility and thermomechanical processing (specifically the final annealing temperature). (1) Detailed microstructural analyses using analytical electron microscopy (AEM) techniques showed that the materials containing dendritic-type intergranular M7C3 carbides were also more resistant to SCC initiation and propagation. This type of analysis has been extended to the evaluation of a 0.062 wt.% C Alloy 600 plate in three conditions (as-received, and heat-treated for 1 week at 982°C and water-quenched, and annealed for 24h at 1075°C and furnace-cooled). Tests were performed in PWR environments using fatigue precracked compact tension (CT) samples. In addition, detailed microstructural analyses using light optical metallography (LOM) and AEM were performed to fully characterize each material condition. The SCC fracture morphology was evaluated using scanning electron microscopy (SEM).

LOM examination of the as-received material indicated a “good” microstructure, with carbide-decorated grain boundaries as well as intragranular carbides.

Type
Oxidation, Corrosion, and Protective Coatings
Information
Microscopy and Microanalysis , Volume 3 , Issue S2: Proceedings: Microscopy & Microanalysis '97, Microscopy Society of America 55th Annual Meeting, Microbeam Analysis Society 31st Annual Meeting, Histochemical Society 48th Annual Meeting, Cleveland, Ohio, August 10-14, 1997 , August 1997 , pp. 783 - 784
Copyright
Copyright © Microscopy Society of America 1997

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References

Webb, G.L. and Burke, M.G., in Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Eds. Airey, G.Pet al. (NACE, 1995) 41.Google Scholar
Rios, R., Magnin, T., Noel, D. and de Bouvier, O., Met Trans. 26A (1995) 925.10.1007/BF02649089CrossRefGoogle Scholar
Some SCC specimens were kindly provided by D.J. Perry of KAPL, Inc., Lockheed Martin Corp.Google Scholar