Study on Mechanical and Corrosion Properties of Zr-4 and Zr-1Nb Alloy After Xe Ions Irradiation

被引：0

作者：

Quan, Qiwei ^{[1
]}

Liu, Xiangbing ^{[1
]}

Zhao, Wenzeng ^{[2
]}

Wu, Yichu ^{[2
]}

Xu, Chaoliang ^{[1
]}

Zhang, Yanwei ^{[1
]}

Li, Yuanfei ^{[1
]}

Qian, Wangjie ^{[1
]}

Jia, Wenqing ^{[1
]}

Yin, Jian ^{[1
]}

机构：

[1] Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu, Suzhou

[2] School of Physics and Technology, Wuhan University, Wuhan

来源：

Cailiao Daobao/Materials Reports | 2024年 / 38卷 / 18期

基金：

中国国家自然科学基金;

关键词：

corrosion resistance; ions irradiation; irradiation harden; zirconium alloy;

D O I：

10.11896/cldb.23020010

中图分类号：

学科分类号：

摘要：

In order to study the performance of two typical fuel cladding zirconium alloys Zr-4 and Zr-1Nb after irradiation, this study used 5.0 MeV Xe ions to irradiate the zirconium alloys up to 4.0 dpa at room temperature, and carried out the corrosion experiment at 360 ℃/18.6 MPa, 0.01 mol/L LiOH solution for 28 d. Combined with nano-indentation, SEM and TEM, the irradiation hardening effect, the morphology of oxidation film and the change of second phase were characterized, discussing the effect of irradiation on corrosion. The result showed that both zirconium alloys produced irradiation hardening after Xe ion irradiation, with Zr-1Nb being more significant than Zr-4. The corrosion resistance of Zr-4 was better than Zr-1Nb in 28 d of simulated environmental corrosion. Ions irradiation increased the corrosion weight gain and caused the second phase amorphous, and the irradiation enhancing corrosion effect was more pronounced for Zr-1Nb. The research could help understand the irradiation effects of zirconium alloys and provide a reference for the development of new cladding zirconium alloy materials. © 2024 Cailiao Daobaoshe/ Materials Review. All rights reserved.

引用

共 27 条

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