AP1000蒸汽发生器地震反应分析及参数敏感性研究  

Seismic Analysis and Parameter Sensitivity Studies for the Steam Generator of AP1000

作　　者：钱浩[1] 徐定耿[1] 杨仁安[1] 梁星筠[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核电工程与技术》2013年第1期18-23,共6页Nuclear Power Engineering and Technology

摘　　要：蒸汽发生器是排出反应堆堆芯热量的主要设备，是反应堆冷却剂系统压力边界的一部分。本文通过建立详细的AP1000蒸汽发生器分析模型。以两台蒸汽发生器与一回路管道和反应堆压力容器组成的系统为对象．进行地震反应分析。在所得反应的基础上重点对各参数的敏感性作了研究．其中包括两台蒸汽发生器相互作用、支撑与抗振条设置等的影响，总结了它们对分析和设计的指导性价值。分析结果表明，设备支撑和抗振条设置对地震反应结果甚为敏感，后续电站蒸汽发生器研发时需着重考虑这些因素。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. The analysis model of AP1000 SG is created and the seismic analysis is performed with RCS model. In addition, parameter sensitivities of seis- mic results are studied for analysis and design, such as the effect of another SG, support, anti-vibration bars （AVBs）, and so on. The comments are expected to be significant for future analysis and design. The analysis result indicates that seismic results are sensitive to support and AVB setting, which should be focus of fu- ture new type NPP SG＇s research and design.

关 键 词：AP1000 蒸汽发生器 地震反应分析 参数敏感性 

分 类 号：TM623[电气工程—电力系统及自动化]