Uniform and "'nodule" corrosion of zirconium alloys under service conditions

被引：1
|
作者：
Perekhozhev, VI [1 ]
Sinel'nikov, LP [1 ]
Timokhin, AN [1 ]
Averin, SA [1 ]
Chernetsov, MV [1 ]
Kuznetsov, VP [1 ]
机构：
[1] SF NIKIET, Res & Design Inst Power Engn, Ekaterinburg, Russia
来源：
METAL SCIENCE AND HEAT TREATMENT | 2003年 / 45卷 / 9-10期
关键词：
Oxidation; Nodule; Zirconium; Power Plant; Nuclear Power Plant;
D O I：
10.1023/B:MSAT.0000009787.03101.93
中图分类号：
TF [冶金工业];
学科分类号：
0806 ;
摘要：
Results concerning uniform and nodule (local) corrosion obtained in SF NIKIET are reviewed. The applicability of the electrotechnical theory of high-temperature oxidation of metals to zirconium alloys is analyzed. The conditions of occurrence of nodule corrosion are determined, and the results of a study of process channels and fuel assemblies of RBMK reactors after service at nuclear power plants (NPP) are generalized.
引用
收藏
页码：390 / 395
页数：6
相关论文
共 50 条
  • [1] Uniform and “Nodule” Corrosion of Zirconium Alloys under Service Conditions
    V. I. Perekhozhev
    L. P. Sinel'nikov
    A. N. Timokhin
    S. A. Averin
    M. V. Chernetsov
    V. P. Kuznetsov
    Metal Science and Heat Treatment, 2003, 45 : 390 - 395
  • [2] Temperature sensitivity and transition kinetics of uniform corrosion of zirconium alloys in superheated steam
    Liao, Jingjing
    Cheng, Zhuqing
    Zhang, Wei
    Tang, Yan
    Yang, Zhongbo
    Wu, Jun
    Qiu, Shaoyu
    HELIYON, 2024, 10 (12)
  • [3] Waterside Corrosion in Zirconium Alloys
    Motta, Arthur T.
    JOM, 2011, 63 (08) : 63 - 67
  • [4] Uniform corrosion of zirconium alloy 4 under isothermal oxidation at high temperature
    Prajitno, D. H.
    NEUTRON AND X-RAY SCATTERING IN MATERIALS SCIENCE AND BIOLOGY, 2008, 989 : 73 - 76
  • [5] Hydrogen diffusion process in the oxides formed on zirconium alloys during corrosion in pressurized water reactor conditions
    Tupin, Marc
    Martin, Frantz
    Bisor, Caroline
    Verlet, Romain
    Bossis, Philippe
    Chene, Jacques
    Jomard, Francois
    Berger, Pascal
    Pascal, Serge
    Nuns, Nicolas
    CORROSION SCIENCE, 2017, 116 : 1 - 13
  • [6] Corrosion kinetics under high pressure of steam of pure zirconium and zirconium alloys followed by in situ thermogravimetry
    Dali, Yacoub
    Tupin, Marc
    Bossis, Philippe
    Pijolat, Michele
    Wouters, Yves
    Jomard, Francois
    JOURNAL OF NUCLEAR MATERIALS, 2012, 426 (1-3) : 148 - 159
  • [7] Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditions
    Kim, Taeho
    Choi, Kyoung Joon
    Yoo, Seung Chang
    Lee, Yunju
    Kim, Ji Hyun
    CORROSION SCIENCE, 2018, 131 : 235 - 244
  • [8] Corrosion Behavior of Zirconium Alloys with Nb and Cr Addition
    Kim, Yoon-Ho
    Mok, Yong-Kyoon
    Kim, Hyun-Gil
    Lee, Jong-Hyeon
    KOREAN JOURNAL OF MATERIALS RESEARCH, 2015, 25 (08): : 376 - 385
  • [9] Systematic approach to predicting corrosion of zirconium alloys in the water coolant of nuclear reactors
    V. G. Kritskii
    I. G. Berezina
    Atomic Energy, 2011, 110 : 265 - 276
  • [10] Review of stress fields in Zirconium alloys corrosion scales
    Guerain, M.
    Duriez, C.
    Grosseau-Poussard, J. L.
    Mermoux, M.
    CORROSION SCIENCE, 2015, 95 : 11 - 21
12345