Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
5454113 | Journal of Nuclear Materials | 2017 | 9 Pages |
Abstract
EK-181 is a low-activation ferritic/martensitic steel that is an attractive candidate for in-core component materials for both fast reactors and fusion reactors. To assess the effect of microstructural engineering on radiation response, two variants of EK-181 were studied: one in an annealed condition and the other subject to severe plastic deformation. These specimens were irradiated with 3.5 MeV Fe self-ions up to 400 peak displacements per atom (dpa) at temperatures ranging from 400 °C to 500 °C. The deformation did not suppress swelling over the whole irradiated region. Instead, deformed samples showed higher swelling in the near-surface region. Void swelling was found to be correlated with grain boundary instability. Significant grain growth occurred when steady-state void growth started.
Related Topics
Physical Sciences and Engineering
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Nuclear Energy and Engineering
Authors
E. Aydogan, T. Chen, J.G. Gigax, D. Chen, X. Wang, P.S. Dzhumaev, O.V. Emelyanova, M.G. Ganchenkova, B.A. Kalin, M. Leontiva-Smirnova, R.Z. Valiev, N.A. Enikeev, M.M. Abramova, Y. Wu, W.Y. Lo, Y. Yang, M. Short, S.A. Maloy, L. Shao,