期刊
JOURNAL OF NUCLEAR MATERIALS
卷 428, 期 1-3, 页码 176-182出版社
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2011.12.009
关键词
-
资金
- EMIR network
Oxide Dispersion Strengthened (ODS) ferritic-martensitic steels are considered for nuclear applications as structural components for fusion or fission reactors. To ensure good performances in service, the stability under irradiation of the microstructure and especially of Y-Ti-O nanoclusters have to be assessed. In situ Transmission Electron Microscopy has been performed to follow the Y-Ti-O nano-oxides dispersed in a Fe18Cr1W0.3Ti + 0.6Y(2)O(3) ODS material under ion-irradiation at 500 degrees C. Microstructural examinations using bright and dark field mode showed that Y-Ti-O nano-precipitates (5 nm) are still present after irradiation up to 45 dpa. However, some larger oxides seem to be more affected by irradiation at 45 dpa (creation of point defects, interface and shape modification). (C) 2012 Elsevier B.V. All rights reserved.
作者
我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。
推荐
暂无数据