Radiation effects on the microstructure of a 9Cr-ODS alloy

被引：5
|
作者：
Gan, J. [1 ]
Allen, T. R. [2 ]
Birtcher, R. C. [3 ]
Shutthanandan, S. [4 ]
Thevothasan, S. [4 ]
机构：
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
[2] Univ Wisconsin, Madison, WI 53706 USA
[3] Argonne Natl Lab, Argonne, IL 60439 USA
[4] Pacific NW Natl Lab, Richland, WA 99352 USA
来源：
JOM | 2008年 / 60卷 / 01期
关键词：
D O I：
10.1007/s11837-008-0003-5
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700 degrees C to doses lip to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in Size and increase in density with increasing ir radiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures lip to 700 degrees C and doses lip to 1.50 dpa.
引用
收藏
页码：24 / 28
页数：5
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