摘要
蒸汽发生器是排出反应堆堆芯产生热量的主要设备,是反应堆冷却剂系统压力边界的一部分。其为抗震I类设备,须对其进行地震反应分析。本文建立了蒸汽发生器地震反应分析模型,地震反应分析模型包含汽水分离器组件和管束组件等内件。两个蒸汽发生器模型与一回路管道和压力容器串联,进行地震反应分析,获得地震载荷下的应力结果。同时,本文还就地震反应分析结果对各参数的敏感性做了研究,其中包括另一台蒸汽发生器、支撑、抗振条设置等的影响。研究结果表明,地震反应结果对设备支撑和抗振条设置特别敏感。本文总结了这些参数对分析和设计的指导性意见,供后续核电站蒸汽发生器设计和研发时参考和关注。
Background： The steam generator （SG） serves as the primary means for removing the heat generated within the reactor core and is part of the reactor coolant system （RCS） pressure boundary. Purpose： Seismic analysis is required for SG, whose seismic category is Cat. I. Methods： The analysis model of SG is created with moisture separator assembly and tube bundle assembly herein. The seismic analysis is performed with RCS pipe and Reactor Pressure Vessel （RPV）. Results： The seismic stress results of SG are obtained. In addition, parameter sensitivities of seismic analysis results are studied, such as the effect of another SG7 support, anti-vibration bars （AVBs）, and so on. Our results show that seismic results are sensitive to support and AVBs setting. Conclusions： The guidance and comments on these parameters are summarized for equipment design and analysis, which should be focused on in future new type NPP SG＇s research and design.
出处
《核技术》
CAS
CSCD
北大核心
2013年第4期11-16,共6页
Nuclear Techniques
