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

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 ...

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Publication status:
Published
Peer review status:
Peer reviewed

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Institution:
University of Oxford
Division:
MPLS
Department:
Materials
Role:
Author
Publisher:
Materials Research Society
Journal:
Materials Research Society Symposium Proceedings More from this journal
Volume:
1519
Pages:
72-81
Publication date:
2013-01-01
DOI:
EISSN:
1946-4274
ISSN:
0272-9172
Language:
English
Pubs id:
pubs:466919
UUID:
uuid:b6a83b4f-847c-46c3-878c-04b0a8375291
Local pid:
pubs:466919
Source identifiers:
466919
Deposit date:
2014-06-17

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