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Micromechanical testing of oxidized grain boundaries in Nickel alloys from nuclear reactors

Published online by Cambridge University Press:  23 January 2013

Sergio Lozano-Perez ,
Helen Dugdale ,
David E J Armstrong ,
Takumi Terachi ,
Takuyo Yamada ,
Edmund Tarleton  and
Steve G Roberts
Sergio Lozano-Perez
Affiliation:
Department of Materials, University of Oxford, Oxford OX1 3PH, United Kingdom.
Helen Dugdale
Affiliation:
Department of Materials, University of Oxford, Oxford OX1 3PH, United Kingdom.
David E J Armstrong
Affiliation:
Department of Materials, University of Oxford, Oxford OX1 3PH, United Kingdom.
Takumi Terachi
Affiliation:
INSS, 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan.
Takuyo Yamada
Affiliation:
INSS, 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan.
Edmund Tarleton
Affiliation:
Department of Materials, University of Oxford, Oxford OX1 3PH, United Kingdom.
Steve G Roberts
Affiliation:
Department of Materials, University of Oxford, Oxford OX1 3PH, United Kingdom.
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Abstract

The fracture behaviour of individual grain boundaries has been studied in order to understand the mechanisms controlling stress corrosion cracking in nuclear reactors. In particular, the role of oxidation in facilitating crack initiation and propagation has been reviewed. Nickel alloys from pressurized water reactors (PWRs) have been tested in simulated primary water conditions to induce grain boundary oxidation. Microcantilevers containing an oxidized grain boundary plane have been prepared and tested for fracture. The brittle nature of the oxide was demonstrated and the required stress to fracture measured.

Keywords

stress/strain relationshipsteeloxidation
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1519: Symposium MM – Materials under Extreme Environments , 2013 , mrsf12-1519-mm10-03
Copyright
Copyright © Materials Research Society 2013

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References

REFERENCES

Scott, P.M. and Le Calvar, M., in Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (NACE, 1993), pp. 657.Google Scholar
Lozano-Perez, S., Yamada, T., Terachi, T., Schröder, M., English, C.A., Smith, G.D.W., Grovenor, C.R.M. and Eyre, B.L., Acta Materialia 57 5361–5381 (2009).10.1016/j.actamat.2009.07.040CrossRefGoogle Scholar
Terachi, T., Yamada, T., Arioka, K. and Lozano Perez, S., in Proceedings of the International Symposium on Research for Ageing Management of Light Water Reactors and Its Future Trend edited by: Eyre, B., Kimura, I. (INSS, 2007), pp. 215–228.Google Scholar
Armstrong, D.E.J., Wilkinson, A.J. and Roberts, S.G., Philosophical Magazine Letters 91 394–400 (2011).10.1080/09500839.2011.573813CrossRefGoogle Scholar
Lozano-Perez, S., Kruska, K., Iyengar, I., Terachi, T. and Yamada, T., Corros. Sci. 56 78–85 (2012).10.1016/j.corsci.2011.11.021CrossRefGoogle Scholar
Trebbia, P. and Bonnet, N., Ultramicroscopy 34 165–178 (1990).10.1016/0304-3991(90)90070-3CrossRefGoogle Scholar
Lozano-Perez, S., de Castro Bernal, V. and Nicholls, R.J., Ultramicroscopy 109 1217–1228 (2009).10.1016/j.ultramic.2009.05.006CrossRefGoogle Scholar