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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

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