Hostname: page-component-cd9895bd7-dzt6s Total loading time: 0 Render date: 2024-12-25T13:11:37.638Z Has data issue: false hasContentIssue false

Aqueous Corrosion of WCLL Breeder Blanket Structural Material Eurofer-97 for Nuclear Fusion Reactors

Published online by Cambridge University Press:  22 July 2022

David Kumar*
Affiliation:
Interface Analysis Centre, Department of Physics, University of Bristol, Bristol, United Kingdom
Robert Burrows
Affiliation:
National Nuclear Laboratory, Stonehouse, Gloucestershire, United Kingdom
Lucy Platts
Affiliation:
National Nuclear Laboratory, Stonehouse, Gloucestershire, United Kingdom
Angus Siberry
Affiliation:
Interface Analysis Centre, Department of Physics, University of Bristol, Bristol, United Kingdom
Aidan Gunn
Affiliation:
Interface Analysis Centre, Department of Physics, University of Bristol, Bristol, United Kingdom
Mariia Zimina
Affiliation:
Interface Analysis Centre, Department of Physics, University of Bristol, Bristol, United Kingdom
Chris Harrington
Affiliation:
UK Atomic Energy Authority, Culham Centre for Fusion Energy, Abingdon, United Kingdom
Ross Springell
Affiliation:
Interface Analysis Centre, Department of Physics, University of Bristol, Bristol, United Kingdom
Tomas Martin
Affiliation:
Interface Analysis Centre, Department of Physics, University of Bristol, Bristol, United Kingdom
Alessandro Del Nevo
Affiliation:
Fusion and Technology for Nuclear Safety and Security Department, ENEA, Italy
*
*Corresponding author: [email protected]

Abstract

Image of the first page of this content. For PDF version, please use the ‘Save PDF’ preceeding this image.'
Type
Correlative Microscopy and High-Throughput Characterization for Accelerated Development of Materials in Extreme Environments
Copyright
Copyright © Microscopy Society of America 2022

References

Kumar, D. et al. , Journal of Nuclear Materials 554 (2021), p. 153084. https://doi.org/10.1016/j.jnucmat.2021.153084CrossRefGoogle Scholar
R Aymar, ., Barabaschi, P., and Shimomura, Y., Plasma Phys. Control. Fusion 44 (2002), p. 519–565.CrossRefGoogle Scholar
Harrington, C. et al. , Fusion Engineering and Design 146 (2019), p. 478-481. https://doi.org/10.1016/j.fusengdes.2018.12.095CrossRefGoogle Scholar
R Burrows, . et al. , Fusion Engineering and Design 136 (2018), p. 1000-1006. https://doi.org/10.1016/j.fusengdes.2018.04.054CrossRefGoogle Scholar
Tong, Z., and Dai, Y.. Journal of Nuclear Materials 398 (2010), p. 4348. https://doi.org/10.1016/j.jnucmat.2009.10.008CrossRefGoogle Scholar
Harries, D. R. et al. , Journal of Nuclear Material 191-194 (1992), p. 9299. https://doi.org/10.1016/S0022-3115(09)80015-9CrossRefGoogle Scholar
Elements within this work have been carried out within the framework of the EUROfusion Consortium receiving part-funding from the Euratom research and training programme 2014-2018 and 2019-2020 under grant agreement No 633053 and from the RCUK [grant number EP/T012250/1]. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Authors acknowledge the work of Dr C. Jones, Prof. D. Cherns, Dr I. Griffiths, and Dr J. C. Eloi in their FIB, TEM, STEM training and usage.Google Scholar