压水堆核电厂结构材料腐蚀防护设计与老化管理
Protection Design and Ageing Management for Corrosion of Structural Materials in PWR Nuclear Power Plants
摘 要
概述了压水堆核电厂典型的结构材料种类与腐蚀类型，并以此为基础介绍了常见的腐蚀防护设计手段及腐蚀老化管理的理念和方法，对明确压水堆核电厂设备/部件、材料、环境、腐蚀、防护、老化管理间的相互关系具有参考价值，为确保机组的安全与经济运行提供重要保障。
结构材料
腐蚀与防护
水化学控制
防护涂层设计
老化管理
pressurized water reactor (PWR)
structural material
corrosion and protection
water chemistry control
protective coating design
ageing management
Abstract
The typical types of structural materials and corrosions in pressurized water reactors (PWRs) as well as the pertinent corrosion protection designs and ageing management concepts and methodologies are reviewed. Achievement of this paper will have the reference value to understand the correlation among components, materials, environments, corrosion, protection and ageing management, to provide the basics to ensure safe and economic operation of PWRs.
中图分类号 TG172 DOI 10.11973/fsyfh201607003
所属栏目 核电设备材料防护
基金项目
收稿日期 2016/5/25
修改稿日期
网络出版日期
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联系人作者xuxl@snerdi.com.cn
备注徐雪莲（1961-）,研究员级高级工程师,主要从事核电结构材料的腐蚀与防护研究,核用涂料的设计与开发及核电设备老化管理等
引用该论文: XU Xuelian,GONG Yi,LIU Xiaoqiang,BAO Yichen,SHI Xiuqiang,MENG Fanjiang. Protection Design and Ageing Management for Corrosion of Structural Materials in PWR Nuclear Power Plants[J]. Corrosion & Protection, 2016, 37(7): 534
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【7】丁亚平,徐雪莲. 压水堆核电厂长寿命化的腐蚀损伤问题\[J\]. 腐蚀与防护,2001,22(11):489493,497.
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【9】STEINBRCK M,BTTCHER M. Air oxidation of Zircaloy4,M5 and ZIRLOTM cladding alloys at high temperatures\[J\]. Journal of Nuclear Materials,2011,414(2):276285.
【10】HAYASHI H,HASHIMOTO N,OHNUKI S. Stability of precipitates in ZIRLO under high energy particle irradiation\[J\]. Journal of Nuclear Materials,2013,442(1/3):S830S833.
【11】BELL B D C,MURPHY S T,BURR P A,et al. The influence of alloying elements on the corrosion of Zr alloys\[J\]. Corrosion Science,2016(105):3643.
【12】韩向臻,攸国顺,孙微. 第三代反应堆AP1000和EPR的堆芯核设计\[J\]. 中国科技信息,2013,25(3):5053.
【13】胡源,顾楠. 核级锆材:重复建设需深思\[J\]. 中国有色金属,2015,22(15):4243.
【14】赵文金,周邦新,苗志,等. 我国高性能锆合金的发展\[J\]. 原子能科学技术,2005,39(S1):29.
【15】周军,李中奎. 轻水反应堆（LWR）用包壳材料研究进展\[J\]. 中国材料进展,2014,33(9/10):554559.
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【18】HWANG I S,PARK I G. Control of alkaline stress corrosion cracking in pressurizedwater reactor steam generator tubing\[J\]. Corrosion,1999,55(6):616625.
【19】龚嶷,徐雪莲. 压水堆核电厂蒸汽发生器老化机理及其影响因素\[J\]. 腐蚀与防护,2014,35(2):163168,174.
【20】HARROD D,GOLD R,JACKO R. Alloy optimization for PWR steam generator heattransfer tubing\[J\]. JOM,2001,53(7):1417.
【21】TAN L,ALLEN T R,YANG Y. Corrosion behavior of alloy 800H (Fe21Cr32Ni) in supercritical water\[J\]. Corrosion Science,2011,53(2):703711.
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