压力容器2025，Vol.42Issue(5)：38-45,8.DOI:10.3969/j.issn.1001-4837.2025.05.005
压水堆核电厂反应堆一回路承压管道高周热疲劳分析探讨
Analysis and discussion on high-cycle thermal fatigue of reactor primary loop pressure-bearing pipelines in pressurized water reactor nuclear power plants
摘要
Abstract
To address the high-cycle thermal fatigue issue easily occurring in the primary loop pressure-bearing pipelines of pressurized water reactor nuclear power plants during long-term operation,an in-depth analysis was conducted using a combination of numerical simulation and online monitoring.Numerical simulation results show that under an inlet temperature fluctuation frequency of 5×10-3 Hz,the temperature variation near the weld is significant;whereas under a high-frequency fluctuation of 2×10-2 Hz,the temperature variation is significantly attenuated,with an inner wall temperature attenuation rate of up to 82.7%.The study developed TECMAN fatigue management analysis software,which can effectively monitor thermal stratification and thermal shock phenomena of the fluid inside the pipeline,and has been successfully applied in a large domestic pressurized water reactor nuclear power unit.The research provides a scientific basis and technical support for thermal fatigue management of primary loop pressure-bearing pipelines in nuclear power plants,contributing to ensuring the safe and stable operation of nuclear power plants.关键词
承压管道/高周疲劳/振荡频率/裂纹萌生/裂纹扩展Key words
pressure-bearing pipeline/high-cycle fatigue/oscillation frequency/crack initiation/crack propagation分类
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赵万祥,徐成杰,陈明亚,林磊,余伟炜,彭群家,马官兵,韩姚磊..压水堆核电厂反应堆一回路承压管道高周热疲劳分析探讨[J].压力容器,2025,42(5):38-45,8.基金项目
国家自然科学基金项目(U21B2076,U21132076) （U21B2076,U21132076）
