Research Progress on Corrosion Behavior of Secondary Phase Precipitate of Zirconium Alloy Fuel Cladding in Pressurized Water Reactor

被引：0
|
作者：
Wang, Depeng [1 ]
Li, Yifeng [1 ]
Liang, Xue [2 ]
Peng, Jianchao [2 ]
Li, Qiang [2 ]
Yao, Meiyi [1 ]
Zhou, Bangxin [1 ]
机构：
[1] Institute of Materials, Shanghai University, Shanghai,200072, China
[2] Laboratory for Microstructures, Shanghai University, Shanghai,200444, China
来源：
Xiyou Jinshu Cailiao Yu Gongcheng/Rare Metal Materials and Engineering | 2023年 / 52卷 / 02期
关键词：
Compendex;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Microstructure
引用
收藏
页码：753 / 762
相关论文
共 50 条
  • [31] Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests
    Burukin, A. V.
    Dolgov, A. I.
    Izhutov, A. L.
    Il'in, P. A.
    Kalygin, V. V.
    Mokeichev, M. A.
    Ugryumov, A. V.
    Dolgov, Yu. N.
    ATOMIC ENERGY, 2020, 128 (03) : 191 - 195
  • [32] Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests
    A. V. Burukin
    A. I. Dolgov
    A. L. Izhutov
    P. A. Il’in
    V. V. Kalygin
    M. A. Mokeichev
    A. V. Ugryumov
    Yu. N. Dolgov
    Atomic Energy, 2020, 128 : 191 - 195
  • [33] Current progress of Cr-coated zirconium alloy cladding for accident tolerant fuel
    Duan Z.
    Chen P.
    Zhou Y.
    Gao S.
    Jiao Y.
    Yin C.
    He L.
    He Jishu/Nuclear Techniques, 2022, 45 (03):
  • [34] Interface Damage Behavior of Zirconium Alloy Cladding Under Fretting Corrosion Environment
    Jiao Y.
    Li Z.
    Pu Z.
    Ren Q.
    Zheng M.
    Wu Y.
    Qiu S.
    Zhongguo Biaomian Gongcheng/China Surface Engineering, 2022, 35 (04): : 41 - 49
  • [35] CORROSION BEHAVIOR OF NICKEL-CHROMIUM-IRON ALLOY 600 IN BORATED PRESSURIZED WATER REACTOR ENVIRONMENTS
    VANROOYEN, D
    COPSON, HR
    BERRY, WE
    CORROSION, 1969, 25 (05) : 194 - +
  • [36] Creep Tests Research on a New Zirconium Alloy for Nuclear Fuel Cladding Tubes
    Meng, Xinming
    Xue, Fei
    Yu, Weiwei
    Guo, Hongmei
    NEW TRENDS IN MECHATRONICS AND MATERIALS ENGINEERING, 2012, 151 : 47 - +
  • [37] Optimization of N18 Zirconium Alloy for Fuel Cladding of Water Reactors
    B.X.Zhou 1
    Journal of Materials Science & Technology, 2012, 28 (07) : 606 - 613
  • [38] Optimization of N18 Zirconium Alloy for Fuel Cladding of Water Reactors
    Zhou, B. X.
    Yao, M. Y.
    Li, Z. K.
    Wang, X. M.
    Zhou, J.
    Long, C. S.
    Liu, Q.
    Luan, B. F.
    JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2012, 28 (07) : 606 - 613
  • [39] Thorium Utilization in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding
    Vaidyanathan, Swaminathan
    NUCLEAR TECHNOLOGY, 2020, 206 (10) : 1538 - 1552
  • [40] Stress Corrosion Cracking Behavior of Alloy 182 Weld in Pressurized Water Reactor Primary Water Environment at 325°C
    Lima, L. I. L.
    Schvartzman, M. M. A. M.
    Figueiredo, C. A.
    Bracarense, A. Q.
    CORROSION, 2011, 67 (08)
12345