Irradiation hardening and embrittlement in high-Cr oxide dispersion strengthened steels

被引:12
作者
Oh, S. [1 ]
Lee, J. S. [2 ]
Jang, C. [1 ]
Kimura, A. [3 ]
机构
[1] Korea Adv Inst Sci & Technol, Dept Nucl & Quantum Engn, Taejon 305701, South Korea
[2] Korea Inst Nucl Safety, Taejon 305338, South Korea
[3] Kyoto Univ, Inst Adv Energy, Kyoto 6110011, Japan
关键词
RESEARCH-AND-DEVELOPMENT; FERRITIC STEELS;
D O I
10.1016/j.jnucmat.2008.12.144
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The effects of neutron irradiation on the mechanical properties of high-Cr oxide dispersion strengthened (ODS) ferritic steels were observed. The materials used were produced by varying the Cr content from 14 to 22 wt% while maintaining the yittria contents within the range of 0.36-0.38 wt%. The ODS steels were irradiated in JMTR at 300, 420 and 550 degrees C to 5.56 x 10(20) n/cm(2) (>1 MeV). Charpy impact tests were performed between -150 degrees C and room temperature. The upper shelf energy (USE) of all ODS steel samples were reduced after irradiation. However, the reduction became smaller as the irradiation temperature increased. When the ODS steels were irradiated at 300 and 420 degrees C, the ductile-to-brittle transition temperature increased significantly. Tensile tests of the ODS steels irradiated at 300 degrees C were performed at room temperature with a strain rate of 6.7 x 10(-4) s(-1). The yield stress and tensile strength of the irradiated ODS alloys increased significantly, and the level of irradiation hardening increased with the Cr content. Anisotropy was not observed in the yield stress and tensile strength but was observed in the elongation. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:503 / 506
页数:4
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