聚丙烯酸对不同Cr含量材料流动加速腐蚀性能的影响研究  

Effect of Polyacrylic Acid on Flow Accelerated Corrosion Behavior of Materials with Different Cr Content

作　　者：吕刘帅 高路杨 但体纯 胡苧尹 肖调兵 陈银强 LYU Liushuai;GAO Luyang;DAN Tichun;HU Ningyin;XIAO Diaobing;CHEN Yinqiang(China Nuclear Power Operation Technology Corporation.LTD.,Wuhan 430000,China)

机构地区：[1]中核武汉核电运行技术股份有限公司,武汉430000

出　　处：《表面技术》2024年第16期139-150,共12页Surface Technology

摘　　要：目的探究PAA使用中对国内核电机组二回路管道流动加速腐蚀性能的影响。方法依托电加热试验台架,设计流动加速腐蚀试验环路,采用失重法获得有PAA与无PAA挂件试样的腐蚀速率,使用SEM与EDS观察挂件试样腐蚀形貌,研究PAA对不同Cr含量的合金钢材料A106B、A335P22、304的影响。结果在温度为220℃、压力为6.7 MPa、流速为4.68 m/s下,A106B、A335P22以及304不锈钢3种管材无PAA添加时,流动加速腐蚀速率分别为0.1120、0.0686、0 mm/a,添加PAA时FAC腐蚀速率分别为0.0956、0.0669、0 mm/a;5μg/kg~10mg/kg质量浓度的PAA添加对A106B、A335P22以及304不锈钢3种管材FAC腐蚀速率、表面形貌无明显影响。结论220℃时,5μg/kg~10 mg/kg质量浓度的PAA添加对A106B、A335P22以及304不锈钢3种材料流动加速腐蚀环境相容性无明显影响,不会加快其FAC腐蚀;由于PAA的分散作用,添加PAA会对碳钢材料A106B的FAC腐蚀速率具有一定的抑制作用,但对于Cr含量较高的A335P22,304不锈钢无明显影响。During the operation of nuclear power plants,sludge deposits and fouling will form on the secondary side of the steam generator,which will affect the heat transfer of the steam generator and cause the thermal and hydraulic instability of the steam generator.In order to solve the thermal hydraulic instability caused by sludge deposition and scaling,chemical cleaning methods are mostly used in foreign countries to treat deposition and scaling in SG,and most of them are hydromechanical cleaning in China.Research has shown that polyacrylic acid(PAA)has a strong ability to disperse iron oxide and can effectively remove corrosion products on the secondary side of the steam generator,thereby improving the reliability of the steam generator.Although the synthesis research of domestic PAA is relatively mature,there is still no research on the effect of domestic PAA on flow accelerated corrosion.Flow accelerated corrosion(FAC)is the main mechanism for thinning of secondary circuit pipelines,resulting in thinning of pipeline wall thickness,and even causing pipeline failure and bursting.There have been many pipeline leakage and even rupture accidents in history,causing major human and economic losses,which directly affects the safe operation of nuclear power plants and the life safety of nuclear power workers.To ensure the safe and reliable use of domestic PAA in domestic nuclear power units,in this article,FAC performance research experiments were conducted to study the effect of PAA on alloy steel materials A106B,A335P22,304 with different Cr content under high temperature,high pressure,and environmental conditions by adding PAA,so as to explore the effect of PAA on the flow accelerated corrosion performance of secondary circuit pipelines of domestic nuclear power units.Relying on the electric heating test bench,a flow-accelerated corrosion test loop was designed with a blank group without adding PAA and a test group with PAA,and 3 samples were set in each blank group and test group to study the difference in FAC corrosion

关 键 词：PAA 流动加速腐蚀 二回路 

分 类 号：TG174[金属学及工艺—金属表面处理]