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Effects of heavy-ion irradiation on the grain boundary chemistry of an oxide-dispersion strengthened Fe-12 wt.% Cr alloy

Abstract:

Understanding the behaviour of oxide-dispersion strengthened (ODS) ferritic martensitic steels under irradiation is of prime importance in the design of future fusion reactors. Although changes in grain boundary chemistry during irradiation can significantly affect fracture strength, little is known on the behaviour of grain boundaries in ODS steels. Here, the effect of heavy-ion implantation at 500 °C on grain boundary chemistry in a model ODS Fe-12 wt.% Cr alloy was investigated using atom-...

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Publication status:
Published

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Institution:
University of Oxford
Department:
Oxford, MPLS, Materials
Role:
Author
Journal:
JOURNAL OF NUCLEAR MATERIALS
Volume:
417
Issue:
1-3
Pages:
257-261
Publication date:
2011-10-01
DOI:
ISSN:
0022-3115
URN:
uuid:7c55e197-5b3d-4fa3-a5b0-3f92843172e4
Source identifiers:
194662
Local pid:
pubs:194662
Language:
English

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