Study on Fretting Wear of 690TT Alloy Heat Transfer Tube in High Temperature and High Pressure Water Environment

Steam generator (SG) is the key component of primary and secondary circuits in pressurized water reactor (PWR) nuclear power plant. Its integrity is very important for the safe operation of PWR nuclear power plant. During operation, the secondary side flow of SG will cause the vibration of the heat...

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Bibliographic Details
Main Author: CHU Qibao1,2;HUANG Qian3;ZHANG Mengyang4;JIANG Qinglei4;TAN Wei1
Format: Article
Language:English
Published: Editorial Board of Atomic Energy Science and Technology 2023-10-01
Series:Yuanzineng kexue jishu
Subjects:
Online Access:https://www.aest.org.cn/CN/10.7538/yzk.2022.youxian.0878