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The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb
Xu, Yuwen1; Xie, Shijing1; Qiu, Jie1; Yao, Cunfeng2; Yan, Wei3,4; Li, Yanfen3,4; Yang, Chongdou1; Guo, Shaoqiang1; Gu, Long2; Yun, Di1,5
通讯作者Xie, Shijing(xieshijing@xjtu.edu.cn) ; Qiu, Jie(qiu2021@xjtu.edu.cn)
2024-05-01
发表期刊NANOMATERIALS
卷号14期号:9页码:18
摘要Lead-cooled fast reactors exhibit strong inherent safety performance and good economic features, while material degradation due to corrosion and irradiation is still challenging. Oxide dispersion-strengthened steels are one of the promising candidates for fuel cladding materials. The effects of both irradiation and corrosion on ODS steel need to be further studied. In this work, MX-ODS steel was irradiated by Fe ions at 500 degrees C up to 46 dpa. Later, the as-received specimen and the irradiated specimen were used to conduct corrosion tests in oxygen-saturated Pb at 550 degrees C for 1 h. In the as-received specimen, discontinuous oxides penetrated by Pb and Pb in contact with steel matrix were observed, demonstrating unsatisfactory corrosion resistance of the material. However, in the irradiated specimen after corrosion experiment, a protective oxide layer formed and prevented Pb attack. The oxidation behavior differences between the two specimens can be attributed to the defects produced by irradiation and the structural discrepancy in oxides caused by the formation process. A possible mechanism of irradiation on the corrosion is discussed. In the as-received specimen, Fe atoms loss led to voids in the oxides, and lead penetrated the oxides through these voids. In the irradiated specimen, defects left by previous irradiation helped to form a more uniform oxide layer. The adhesive outer magnetite oxide and the Fe ions generated from where grain boundary oxidation developed retarded the presence of voids and made the oxide layer protective.
关键词irradiation ODS steel liquid metal corrosion
资助者National Key Research and Development Program of China
DOI10.3390/nano14090798
收录类别SCI
语种英语
资助项目National Key Research and Development Program of China
WOS研究方向Chemistry ; Science & Technology - Other Topics ; Materials Science ; Physics
WOS类目Chemistry, Multidisciplinary ; Nanoscience & Nanotechnology ; Materials Science, Multidisciplinary ; Physics, Applied
WOS记录号WOS:001220080300001
出版者MDPI
引用统计
文献类型期刊论文
条目标识符http://ir.imr.ac.cn/handle/321006/186119
专题中国科学院金属研究所
通讯作者Xie, Shijing; Qiu, Jie
作者单位1.Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
2.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China
3.Chinese Acad Sci, CAS Key Lab Nucl Mat & Safety Assessment, Inst Met Res, Shenyang 110016, Peoples R China
4.Chinese Acad Sci, Shi Changxu Innovat Ctr Adv Mat, Inst Met Res, Shenyang 110016, Peoples R China
5.Xi An Jiao Tong Univ, State Key Lab Multiphase Flow, Xian 710049, Peoples R China
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GB/T 7714
Xu, Yuwen,Xie, Shijing,Qiu, Jie,et al. The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb[J]. NANOMATERIALS,2024,14(9):18.
APA Xu, Yuwen.,Xie, Shijing.,Qiu, Jie.,Yao, Cunfeng.,Yan, Wei.,...&Yun, Di.(2024).The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb.NANOMATERIALS,14(9),18.
MLA Xu, Yuwen,et al."The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb".NANOMATERIALS 14.9(2024):18.
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