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The Irradiated Microstructure of Ferritic-Martensitic Steel T91 and 9Cr-ODS

Published online by Cambridge University Press:  01 February 2011

J. Gan ,
T. R. Allen ,
J. I. Cole ,
S. Ukai ,
S. Shutthanandan  and
S. Thevuthasan
J. Gan
Affiliation:
Nuclear Technology Division, Argonne National Laboratory, USA
T. R. Allen
Affiliation:
Department of Engineering Physics, The University of Wisconsin, USA
J. I. Cole
Affiliation:
Nuclear Technology Division, Argonne National Laboratory, USA
S. Ukai
Affiliation:
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Japan
S. Shutthanandan
Affiliation:
Enviromental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, USA
S. Thevuthasan
Affiliation:
Enviromental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, USA
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Abstract

A ferritic steel T91 and an oxide dispersion strengthened (ODS) martensitic steel 9Cr-ODS were irradiated with 5 MeV Ni ions at 500°C at a dose rate of 1.38×10-3 dpa/s to doses of 5, 50 and 150 dpa. Both alloys are iron-based with 9Cr and have been designed for use in higher temperature energy systems. However, the radiation effects on these two alloys are not well characterized. For T91, the irradiated microstructure was dominated by tangled dislocation and precipitates, similar to the unirradiated condition except the presence of large dislocation loops of type a<100>. The microstructure of alloy 9Cr-ODS for both the unirradiated and irradiated cases was dominated by dense dislocations, precipitates and yttrium oxides particles and no dislocation loops were observed. The average size of yttrium oxides particles slightly decreased with dose from 11.8 nm for the unirradiated to 9.1 nm at 150 dpa. No voids were detected for both alloys up to a dose of 150 dpa.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 792: Symposium R – Radiation Effects and Ion Beam Processing of Materials , 2003 , R1.7
Copyright
Copyright © Materials Research Society 2004

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References

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