Pipeline Wall Thinning Behavior of A335P11 Steel under the Condition of Flow Accelerated Corrosion
摘 要
模拟了核电厂常规岛二回路工况,研究了此工况条件下A335P11钢弯管测试段、变径测试段及三通测试段的腐蚀减薄现象。结果表明:发生流动加速腐蚀(FAC)最严重的部位是弯管内弧面、变径管的渐缩管段出口处以及三通测试段的辅出水口处。
Abstract
The conditions of the second loop of the conventional island in nuclear power plant were simulated, and the corrosion thinning behavior of A335P11 pipeline in elbow test section, variable diameter test section and three-way test section under this working condition was studied. The results showed that the most serious site of FAC occured at the inner arc surface of the elbow, the outlet of tapered pipe section of the adjustable pipe, and the auxiliary outlet of the three-way test section.
中图分类号 TG174 DOI 10.11973/fsyfh-201807005
所属栏目 试验研究
基金项目
收稿日期 2017/3/11
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引用该论文: WANG Liangliang,RAO Delin,KUANG Bo,ZHANG Xian,LIU Junliang,CHEN Bao. Pipeline Wall Thinning Behavior of A335P11 Steel under the Condition of Flow Accelerated Corrosion[J]. Corrosion & Protection, 2018, 39(7): 511
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参考文献
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【3】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.
【4】KYUNG H R,TAE H L,JI H K,et al. Online monitoring method using equipotential switching direct current potential drop for piping wall loss by flow accelerated corrosion[J]. Nuclear Engineering and Design,2010,240(3):468-472.
【5】伊成龙. 核电厂二回路管道流动加速腐蚀性能研究[D]. 上海:上海交通大学,2015.
【6】TREVIN S. Flow accelerated corrosion (FAC) in nuclear power plant components[J]. Nuclear Corrosion Science and Engineering,2012(2):186-229.
【7】刘忠. 碳钢在单相流中流动加速腐蚀的数值模拟[J]. 核动力工程,2009,30157:48-53..
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