文献类型：期刊文献

英文题名：A New Repair Criterion for Inconel690 Alloy Steam Generator Tube with Fretting Wear

作者：Tao, Yuchun[1]; Peng, Zhizhen[1]; Kong, Chenguang[2]; Huang, Song[3]; Hui, Hu[3]

机构：[1] Suzhou Nuclear Power Research Institute, Suzhou, 215000, China; [2] Daya Bay Nuclear Power Operation and Management Co., Ltd, Shenzhen, 518124, China; [3] School of Mechanical and Power Engineering, East China University of Science and Technology, University of Science and Technology, Shanghai, 200237, China

年份：2020

卷号：526

期号：1

外文期刊名：IOP Conference Series: Earth and Environmental Science

收录：EI(收录号：20203008964626)

语种：英文

外文关键词：Eddy current testing - Steam generators - Vibrations (mechanical) - Repair - Pressure vessels - Wear of materials - Condition monitoring - Pressurized water reactors - Structural integrity

摘要：Structural integrity assessment of steam generator tubes(SGT) is important for the safety operation of pressurized water reactor. In this work, a repair criterion for Inconel690 SGT with fretting flaw was proposed. Firstly, experiments were conducted to address material strength, eddy current examination and bursting pressure of defected SGT. Then, a numerical method was proposed to predict bursting pressure. At last, all factors were concluded in a simplified statistical method of structural integrity assessment. For anti-vibration bar fretting, Condition Monitoring criterion, Operational Assessment criterion as well as the repair criterion for different inspection interval were proposed. The present criterion can provide reference for the inspection interval considering long-term temporary shutdown or standby. ? Published under licence by IOP Publishing Ltd.