Challenges and Solutions to Localized Thinning Management of Secondary Loop Steam & Water Piping in Nuclear Power Plants
摘 要
工程经验反馈及有关研究表明,轻水反应堆核电厂二回路汽水管道在管道内流体长期作用下,可能会发生流动加速腐蚀、液滴冲击和汽蚀等老化,从而导致管道母材或焊缝发生局部减薄的老化劣化现象。如不进行有效的预防性检测和系统的主动管理,可能会导致管道局部泄漏或破裂。扼要介绍上述老化机理、老化效应、易发生部位、影响因素以及国内外的主要管理方法和实践。重点探讨了检测方法、检测部位、标准化等管理和应对措施的现状、挑战和发展趋势。
Abstract
Engineering feed-backs and research results show that the secondary loop steam & water piping in light water reactor power plants, with the long-term operation of inner-fluid, may suffer from the following aging and degradation phenomena such as flow accelerated corrosion, liquid droplet impingement, cavitation erosion, etc., which may lead to the localized thinning of base metal or weld joint in the pipeline. Without predictive inspection and proactive aging management, the sensitive pipeline may experience local leakage, fracture or rupture. This paper briefly introduces above mentioned aging mechanism, aging effects, sensitive locations, affecting factors, as well as the management methods and practices at home and abroad. The art of status, application and development trend of pipe wall-thickness thinning inspection methods, inspection location, standardization are discussed in detail.
中图分类号 TG174 DOI 10.11973/fsyfh-202009007
所属栏目 核电设备的腐蚀与防护
基金项目 国家科技重大专项(2015ZX06002005;2018ZX06002008)
收稿日期 2020/5/8
修改稿日期
网络出版日期
作者单位点击查看
引用该论文: ZHONG Zhimin,ZHENG Hui,LI Jie. Challenges and Solutions to Localized Thinning Management of Secondary Loop Steam & Water Piping in Nuclear Power Plants[J]. Corrosion & Protection, 2020, 41(9): 39
共有人对该论文发表了看法,其中:
人认为该论文很差
人认为该论文较差
人认为该论文一般
人认为该论文较好
人认为该论文很好
参考文献
【1】钟志民,李劲松,郑会. 核电站二回路汽水管道壁厚管理实践与思考[C]//中国核学会,中国核科学技术进展报告(第二卷)——中国核学会2011年学术年会论文集. 北京:中国原子能出版社,2012:503-509.
【2】刘忠,刘春波,郑玉贵. 碳钢在单相流中流动加速腐蚀的数值模拟[J]. 核动力工程,2009,30(5):48-53.
【3】严卓齐. 流量加速腐蚀对核电站二回路材料影响及对策的研究[D]. 上海:上海交通大学,2007.
【4】KIM J H,KIM I S,ZHENG Y G. Flow-accelerated corrosion behavior of SA106 Gr.C weldment[J]. Materials and Corrosion,2003,54:23-31.
【5】HYUKKI S,KYEONGMO H,CHEONGYEOL C. Numerical case studyon the LDIE degradation occurred in the vent header of a high pressure feedwater heater[J]. World Journal of Nuclear Science and Technology,2014,4:26-32.
【2】刘忠,刘春波,郑玉贵. 碳钢在单相流中流动加速腐蚀的数值模拟[J]. 核动力工程,2009,30(5):48-53.
【3】严卓齐. 流量加速腐蚀对核电站二回路材料影响及对策的研究[D]. 上海:上海交通大学,2007.
【4】KIM J H,KIM I S,ZHENG Y G. Flow-accelerated corrosion behavior of SA106 Gr.C weldment[J]. Materials and Corrosion,2003,54:23-31.
【5】HYUKKI S,KYEONGMO H,CHEONGYEOL C. Numerical case studyon the LDIE degradation occurred in the vent header of a high pressure feedwater heater[J]. World Journal of Nuclear Science and Technology,2014,4:26-32.
相关信息