Journal article

TEM characterization of simultaneous triple ion implanted ODS Fe12Cr

Abstract:: Understanding the behavior of oxide dispersion strengthened (ODS) ferritic/martensitic steels under irradiation is vital in the design of advanced fusion reactors. In this work, a simultaneous triple ion implanted ODS Fe12Cr steel was investigated by transmission electron microscopy in order to determine the effect of irradiation on the grain and dislocation structures, oxide nanoparticles and other secondary phases present in the steel. The ODS steel was irradiated at RT with Fe8+, He+ and H+ at the JANNUS-Saclay facility to a damage of 4.4 dpa. Results show that ODS nanoparticles appear very stable under these irradiation conditions.

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APA Style

De Castro, V., Briceno, M., Lozano-Perez, S., Trocellier, P., Roberts, S., & Pareja, R. (2014). TEM characterization of simultaneous triple ion implanted ODS Fe12Cr. Journal of Nuclear Materials, 455(1-3), 157–161.

MLA Style

De Castro, V, et al. “TEM Characterization of Simultaneous Triple Ion Implanted ODS Fe12Cr.” Journal of Nuclear Materials, vol. 455, nos. 1-3, 2014, pp. 157–61.

Chicago Style

De Castro, V, M Briceno, S Lozano-Perez, P Trocellier, S Roberts, and R Pareja. 2014. “TEM Characterization of Simultaneous Triple Ion Implanted ODS Fe12Cr.” Journal of Nuclear Materials 455 (1-3): 157–61.
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Publisher copy:: 10.1016/j.jnucmat.2014.05.064

Authors

+ De Castro, V More by this author

Role:: Author

+ Briceno, M More by this author

Institution:: University of Oxford
Division:: MPLS
Department:: Materials
Role:: Author

+ Lozano-Perez, S More by this author

Institution:: University of Oxford
Division:: MPLS
Department:: Materials
Role:: Author

+ Trocellier, P More by this author

Role:: Author

+ Roberts, S More by this author

Institution:: University of Oxford
Division:: MPLS
Department:: Materials
Role:: Author

More authors...

Publisher:: Elsevier
Journal:: Journal of Nuclear Materials More from this journal
Volume:: 455
Issue:: 1-3
Pages:: 157-161
Publication date:: 2014-01-01
DOI:: 10.1016/j.jnucmat.2014.05.064
ISSN:: 0022-3115

Language:: English
Pubs id:: pubs:472120
UUID:: uuid:05cbd3a6-bbd0-4b35-9bf3-5ee6d556ad5b
Local pid:: pubs:472120
Source identifiers:: 472120
Deposit date:: 2014-07-05
ARK identifier:: ark:/29072/ora_05cbd3a6bbd04b359bf35ee6d556ad5b

Terms of use

Copyright holder:: Elsevier BV
Copyright date:: 2014
Notes:: Proceedings of the 16th International Conference on Fusion Reactor Materials (ICFRM-16). 2014 Elsevier B.V. All rights reserved.

Licence:: Terms and Conditions of Use for Oxford University Research Archive

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