Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

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 conditi...

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Veröffentlicht in:Journal of nuclear materials 2017-04, Vol.487 (C), p.96-104
Hauptverfasser: Aydogan, E., Chen, T., Gigax, J.G., Chen, D., Wang, X., Dzhumaev, P.S., Emelyanova, O.V., Ganchenkova, M.G., Kalin, B.A., Leontiva-Smirnova, M., Valiev, R.Z., Enikeev, N.A., Abramova, M.M., Wu, Y., Lo, W.Y., Yang, Y., Short, M., Maloy, S.A., Garner, F.A., Shao, L.
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Sprache:eng
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Zusammenfassung: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.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2017.02.006