核电厂非安全级与安全级管道物项地震交互作用研究  

Study on Seismic Interaction of Non-safety and Safety Pipeline Items in Nuclear Power Plants

作　　者：俞向文 徐刚 张亮 刘杰 段林烨 范霁康 Yu Xiangwen;Xu Gang;Zhang Liang;Liu Jie;Duan Linye;Fan Jikang(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China;School of Materials Science and Engineering,Nanjing University of Science and Technology,Nanjing 210094,China)

机构地区：[1]上海核工程研究设计院有限公司,上海200233 [2]南京理工大学,材料科学与工程学院,南京210094

出　　处：《震灾防御技术》2025年第1期119-126,共8页Technology for Earthquake Disaster Prevention

基　　金：国家科技重大专项课题(2018ZX06001001);上海核工程研究设计院有限公司技术产业项目(22FW1087)。

摘　　要：为评估地震灾害中核电厂非安全级管道物项跌落对安全级管道物项的交互作用影响,采用模拟仿真分析与试验验证相结合的方法对管道物项间的冲击过程进行研究。本文建立了管道冲击有限元仿真模型,采用ABAQUS有限元分析软件对核电厂常用安全级管道进行冲击仿真,将管道内截面通流面积减小至50%~55%作为损伤极限,得到不同高度下的冲击极限质量,并采用冲击试验对模拟仿真结果进行验证。研究结果表明,当管道型号规格一定时,其损伤极限主要取决于下落物体的能量,受到高度的影响较小;进行核电厂安全级管道设计布局时,应保证挂在上方的非安全级管道冲击能量小于其能够承受的极限能量。To assess the interaction effects of non-safety pipeline components falling onto safety-grade pipelines in nuclear power plants during an earthquake,this study investigates the impact process through a combination of simulation analysis and experimental validation.A finite element model of pipeline impact is developed,and impact simulations of common safety-level nuclear power pipelines are conducted using ABAQUS software.The damage threshold is defined as a reduction of 50%~55%in the cross-sectional flow area,and the critical impact mass at different heights is determined.The simulation results are validated through impact tests,confirming that for a given pipeline model,the damage threshold is primarily governed by the energy of the falling object,with only a minor influence from height.These findings highlight the importance of ensuring that the impact energy from non-safety pipelines suspended above safety-grade pipelines remains below the structural energy tolerance during the design and layout of nuclear power plant piping systems.

关 键 词：核电厂 地震交互作用 管道物项 模拟仿真 冲击能量 

分 类 号：TL364[核科学技术—核技术及应用]