流动加速腐蚀评价程序CHECWORKS及其核电厂老化管理应用
Flow-accelerated Corrosion Evaluation Computer Program CHECWORKS and Its Application to Ageing Management in Nuclear Power Plants
摘 要
流动加速腐蚀(FAC)是核电厂二回路管线最主要的失效原因之一，严重影响核安全运行。CHECWORKS是美国电力研究院(EPRI)基于FAC经验模型设计开发的商用计算机程序，用以预测FAC速率及其相关的水化学、热工水力参数等。从发展历史、应用现状、程序特点等方面对CHECWORKS进行了综述，为该程序在我国的推广以及在核电厂老化管理中的应用起到积极作用。
二回路
流动加速腐蚀
CHECWORKS
老化管理
nuclear power plant (NPP)
secondary circuit
flow-accelerated corrosion (FAC)
CHECWORKS
ageing management
Abstract
Flow-accelerated corrosion (FAC) is one of the predominant failure causes of the secondary circuit pipelines in nuclear power plants (NPPs), severely affecting the safe operation. CHECWORKS is a commercial FAC evaluation computer program developed from empirical models by Electric Power Research Institute (EPRI) for the sake of predicting the wear rate, the water chemistry and the thermal hydraulic parameters pertaining to FAC. In this paper, the history, application and the features of CHECWORKS are reviewed, which will play an active role not only in the propagation of this program in China but also in its application to the aging management of NPPs.
中图分类号 TG174
所属栏目 专论
基金项目 大型先进压水堆核电重大专项支撑项目(2010ZX06004-018)
收稿日期 2013/7/28
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备注龚嶷(1984-),工程师,博士,从事核电、火电、石化设备管材的腐蚀性能研究及其失效分析,
引用该论文: GONG Yi,XU Xue-lian. Flow-accelerated Corrosion Evaluation Computer Program CHECWORKS and Its Application to Ageing Management in Nuclear Power Plants[J]. Corrosion & Protection, 2014, 35(5): 401
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参考文献
【1】KAIN V,ROYCHOWDHURY S,AHMEDABADI P,et al. Flow accelerated corrosion:Experience from examination of components from nuclear power plants[J]. Engineering Failure Analysis,2011,18:2028-2041.
【2】KAIN V,ROYCHOWDHURY S,MATHEW T,et al. Flow accelerated corrosion and its control measures for the secondary circuit pipelines in Indian nuclear power plants[J]. Journal of Nuclear Materials,2008,383:86-91.
【3】窦一康. 核电厂生命周期全过程的老化管理[J]. 金属热处理,2011,36(1):10-14.
【4】杨振国. 核电装置换热器的失效分析及其解决对策[J]. 金属热处理，2007,32(1):28-35.
【5】YANG Z G,GONG Y,YUAN J Z. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant. Part I:electrochemical corrosion[J]. Materials & Corrosion,2012,63(1):7-17.
【6】GONG Y,YANG Z G,YUAN J Z. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant. Part II:Mechanical degradation[J]. Materials & Corrosion,2012,63(1):18-28.
【7】BARANENKO V I,KUMOV A V,YANCHENKO Y A,et al. Development of software tools for calculating corrosion-erosion wear of pipelines at nuclear power stations[J]. Thermal Engineering,2007,54(12):981-988.
【8】KELLEY A. Checking in with the CHECWORKS Users Group[J]. Nuclear Professional,2007,2:11-13.
【9】DOOLEY R B,CHECXAL V K. Flow-accelerated corrosion of pressure vessels in fossil plants[J]. International Journal of Pressure Vessels and Piping,2000,77:85-90.
【10】张桂英，顾宇，邵杰. 核电站汽水管道流动加速腐蚀的影响因素分析及对策[J]. 动力工程学报，2012,32(2):170-176.
【11】刘春波，郑玉贵. 核电行业中流动促进腐蚀的模型和数值模拟研究进展[J]. 腐蚀科学与防护技术，2008,20(6):436-439.
【12】TOMAROV G V,SHIPKOV A A. Principles of development and specific features relating to practical application of software for solving problems connected with erosion-corrosion of metal in power engineering[J]. Thermal Engineering,2011,58(2):135-142.
【13】BARANENKO V I,PROSVIRNOV A A,EVROPIN S V,et al. Development of software means and normative documentation on the flow-accelerated corrosion of pipelines of nuclear power stations[J]. Thermal Engineering,2012,59(5):378-383.
【14】束国刚，薛飞，遆文新，等. 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.
【15】LEE S H,JEGARL S,CHUNG H S. Demonstration of EPRI CHECWORKS code to predict FAC wear of secondary system pipings of a nuclear power plant[J]. Journal of the Korean Nuclear Society,1999,31(4):375-384.
【16】龚嶷. 石化、火电工业用换热管的腐蚀失效分析及其性能评价[D]. 上海: 复旦大学博士学位论文,2012:15.
【2】KAIN V,ROYCHOWDHURY S,MATHEW T,et al. Flow accelerated corrosion and its control measures for the secondary circuit pipelines in Indian nuclear power plants[J]. Journal of Nuclear Materials,2008,383:86-91.
【3】窦一康. 核电厂生命周期全过程的老化管理[J]. 金属热处理,2011,36(1):10-14.
【4】杨振国. 核电装置换热器的失效分析及其解决对策[J]. 金属热处理，2007,32(1):28-35.
【5】YANG Z G,GONG Y,YUAN J Z. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant. Part I:electrochemical corrosion[J]. Materials & Corrosion,2012,63(1):7-17.
【6】GONG Y,YANG Z G,YUAN J Z. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant. Part II:Mechanical degradation[J]. Materials & Corrosion,2012,63(1):18-28.
【7】BARANENKO V I,KUMOV A V,YANCHENKO Y A,et al. Development of software tools for calculating corrosion-erosion wear of pipelines at nuclear power stations[J]. Thermal Engineering,2007,54(12):981-988.
【8】KELLEY A. Checking in with the CHECWORKS Users Group[J]. Nuclear Professional,2007,2:11-13.
【9】DOOLEY R B,CHECXAL V K. Flow-accelerated corrosion of pressure vessels in fossil plants[J]. International Journal of Pressure Vessels and Piping,2000,77:85-90.
【10】张桂英，顾宇，邵杰. 核电站汽水管道流动加速腐蚀的影响因素分析及对策[J]. 动力工程学报，2012,32(2):170-176.
【11】刘春波，郑玉贵. 核电行业中流动促进腐蚀的模型和数值模拟研究进展[J]. 腐蚀科学与防护技术，2008,20(6):436-439.
【12】TOMAROV G V,SHIPKOV A A. Principles of development and specific features relating to practical application of software for solving problems connected with erosion-corrosion of metal in power engineering[J]. Thermal Engineering,2011,58(2):135-142.
【13】BARANENKO V I,PROSVIRNOV A A,EVROPIN S V,et al. Development of software means and normative documentation on the flow-accelerated corrosion of pipelines of nuclear power stations[J]. Thermal Engineering,2012,59(5):378-383.
【14】束国刚，薛飞，遆文新，等. 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.
【15】LEE S H,JEGARL S,CHUNG H S. Demonstration of EPRI CHECWORKS code to predict FAC wear of secondary system pipings of a nuclear power plant[J]. Journal of the Korean Nuclear Society,1999,31(4):375-384.
【16】龚嶷. 石化、火电工业用换热管的腐蚀失效分析及其性能评价[D]. 上海: 复旦大学博士学位论文,2012:15.
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