核电厂隔震结构主蒸汽管道关键构件抗震性能参数分析研究

Seismic performance parameter analysis of critical components in the main steam pipeline of seismically isolated nuclear power plants

  • 摘要: 针对核电厂主蒸汽管道在隔震大位移作用下的抗震安全性问题,本文基于主蒸汽管道变形能力占比分析识别线型优化后的关键构件,即直管、弯管、空间弯管,并对通过增设弯管的线型优化进行分析研究。论文建立数值分析模型并与试验结果进行对比验证,并进一步对关键构件的径厚比、回转半径和回转半径比值等参数对变形能力和Park-Ang损伤指数的影响规律研究。结果表明在最大循环位移加载下,直管构件径厚比从35.6减小至16.2后,其峰值荷载增大111.7%,损伤指数减小15.2%;弯管构件回转半径由2100 mm增加至3000 mm后,其峰值荷载增大11.8%,损伤指数减小15.7%,减小直管径厚比和增大弯管回转半径均能提高构件的变形能力和改善其损伤状态;空间弯管回转半径比值由0.7增大至1.33后,峰值荷载增大12.8%,但损伤指数增大6.2%,增大回转半径比值,虽能提高空间弯管变形能力,但也导致其更易出现损伤。基于关键构件参数分析结果分析两种不同管道的线型优化方案,并对优化后主蒸汽管道进行地震时程分析,结果表明两种优化方案的峰值应力相较于原方案分别降低40.2%和50.6%,优化管道具有良好的抗震性能,能满足核电厂隔震设计大位移变形要求。

     

    Abstract: To address the seismic safety of the main steam pipeline in nuclear power plants under large displacements induced by base isolation, this study identifies the key components—straight pipes, elbows, and spatial elbows—based on the deformation capacity ratio analysis of the optimized pipeline layout. A layout optimization strategy involving the introduction of elbows is proposed and analyzed in detail. A numerical analysis model is established and validated against experimental results. Parametric studies are further conducted to investigate the influence of diameter-to-thickness ratio, bending radius, and bending radius ratio of key components on deformation capacity and the Park–Ang damage index. The results show that under maximum cyclic displacement loading, reducing the diameter-to-thickness ratio of the straight pipe component from 35.6 to 16.2 increases the peak load by 111.7% and decreases the damage index by 15.2%. Increasing the bending radius of the elbow component from 2100 mm to 3000 mm results in an 11.8% increase in peak load and a 15.7% reduction in the damage index. These findings indicate that reducing the diameter-to-thickness ratio of straight pipes and increasing the bending radius of elbows significantly enhance the deformation capacity and reduce the damage level of the components. For spatial elbows, increasing the bending radius ratio from 0.7 to 1.33 leads to a 12.8% increase in peak load but also a 6.2% increase in the damage index, suggesting that although a larger bending radius ratio improves deformation capacity, it also makes the component more susceptible to damage. Based on the parametric analysis of key components, two pipeline layout optimization schemes are proposed. Time-history seismic analyses of the optimized main steam pipelines are performed, and the results show that the peak stresses of the two optimized schemes are reduced by 40.2% and 50.6%, respectively, compared to the original design. These findings demonstrate that the optimized pipeline configurations exhibit excellent seismic performance and can meet the large-displacement deformation requirements of base-isolated nuclear power plant design.

     

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