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核电厂管道的流体加速腐蚀及其老化管理
引用本文:束国刚,薛飞,遆文新,汪小龙,陆念文,刘鹏,戴忠华.核电厂管道的流体加速腐蚀及其老化管理[J].腐蚀与防护,2006,27(2):72-76.
作者姓名:束国刚  薛飞  遆文新  汪小龙  陆念文  刘鹏  戴忠华
作者单位:1. 广东核电集团苏州热工研究院,苏州,215004
2. 广东核电集团大亚湾核电运营管理有限公司,深圳,518124
摘    要:管道流体加速腐蚀(Flow Accelerated Corrosion)是核电厂和常规电厂碳钢或低合金钢材料汽水管道的一个重要的老化机理,历史上曾发生过美国萨里核电站2号机组和日本美滨核电站3号机组管道破裂等导致人员伤亡的严重事故;本文简要总结了核电厂管道流体加速腐蚀的经验教训、机理及其老化管理的一些方法和对策。

关 键 词:流体加速腐蚀  管道破裂  老化管理
文章编号:1005-748X(2006)02-0072-05
收稿时间:2005-08-31
修稿时间:2005-12-09

FLOW ACCELERATED CORROSION AND AGING MANAGEMENT IN NUCLEAR POWER PLANTS
SHU Guo-gang,XUE Fei,TI Wen-xin,WANG Xiao-long,LU Nian-wen,LIU Peng,DAI Zhong-hua.FLOW ACCELERATED CORROSION AND AGING MANAGEMENT IN NUCLEAR POWER PLANTS[J].Corrosion & Protection,2006,27(2):72-76.
Authors:SHU Guo-gang  XUE Fei  TI Wen-xin  WANG Xiao-long  LU Nian-wen  LIU Peng  DAI Zhong-hua
Affiliation:1. CGNPC Suzhou Nuclear Power Research Institute, Suzhou 215004, China;2. CGNPC Daya Bay Nuclear Operations and Management Co. , Ltd. , Shenzhen 518124, China
Abstract:Flow Accelerated Corrosion(FAC) is an important aging mechanism for water and water/steam piping made of carbon steel or low alloy steel in both nuclear power plants and fossil power plants.Accidents in Surry Unit 2 in USA and Mihama Unit 3 in Japan,caused by pipe rupture due to FAC,led to severe casualties.The experience,mechanism and countermeasures about the aging management of FAC in nuclear power plants are summarized in this paper.
Keywords:Flow accelerated corrosion  Pipe rupture accident  Aging management  
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