Response of 9Cr-ODS steel to proton irradiation at 400 °C

被引：29
|
作者：
He, Jianchao [1 ,2 ]
Wan, Farong [1 ]
Sridharan, Kumar [2 ]
Allen, Todd R. [2 ,3 ]
Certain, A. [4 ]
Wu, Y. Q. [5 ,6 ]
机构：
[1] Univ Sci & Technol Beijing, Sch Mat Sci & Engn, Beijing 100083, Peoples R China
[2] Univ Wisconsin, Dept Engn Phys, Madison, WI 53706 USA
[3] EG&G Idaho Inc, Idaho Natl Engn Lab, Idaho Falls, ID 83401 USA
[4] Pacific NW Natl Lab, Richland, WA 99354 USA
[5] Boise State Univ, Dept Mat Sci & Engn, Boise, ID 83725 USA
[6] Ctr Adv Energy Studies, Idaho Falls, ID 83401 USA
来源：
JOURNAL OF NUCLEAR MATERIALS | 2014年 / 452卷 / 1-3期
基金：
中国国家自然科学基金;
关键词：
OXIDE PARTICLES; ATOM-PROBE; DISPERSION; STABILITY; NANOCLUSTERS; SEGREGATION; EVOLUTION; BEHAVIOR;
D O I：
10.1016/j.jnucmat.2014.05.004
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The stability of Y-Ti-O nanoclusters, dislocation structure, and grain boundary segregation in 9Cr-ODS steels has been investigated following proton irradiation at 400 degrees C with damage levels up to 3.7 dpa. A slight coarsening and a decrease in number density of nanoclusters were observed as a result of irradiation. The composition of nanoclusters was also observed to change with a slight increase of Y and Cr concentration in the nanoclusters following irradiation. Size, density, and composition of the nanoclusters were investigated as a function of nanocluster size, specifically classified to three groups. In addition to the changes in nanoclusters, dislocation loops were observed after irradiation. Finally, radiation-induced enrichment of Cr and depletion of W were observed at grain boundaries after irradiation. (C) 2014 Elsevier B. V. All rights reserved.
引用
收藏
页码：87 / 94
页数：8
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