期刊
JOURNAL OF NUCLEAR MATERIALS
卷 487, 期 -, 页码 96-104出版社
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2017.02.006
关键词
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资金
- U.S. Department of Energy, NEUP program [DE-NE0008297]
- Russian Ministry for Education and Science [14.B25.31.0017]
- MEPhI Academic Excellence Project [02.a03.21.0005]
EK-181 is a low-activation ferriticimartensitic 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 degrees C to 500 degrees 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. (C) 2017 Elsevier B.V. All rights reserved.
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