反应堆系统动力响应的敏感性分析  

Sensitivity Analysis of Reactor System Dynamic Responses

作　　者：黄茜[1] 熊夫睿[1] 兰彬[1] 王碧浩 宋海洋[1] 黄旋[1] 刘帅 Huang Qian;Xiong Furui;Lan Bin;Wang Bihao;Song Haiyang;Huang Xuan;Liu Shuai(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室

出　　处：《核动力工程》2019年第3期75-80,共6页Nuclear Power Engineering

摘　　要：输入参数对反应堆系统动力响应的敏感性分析是优化设计的重要前提。以反应堆系统关键部位的接触刚度和间隙为输入变量,利用Sobol法开展了关键输入参数对地震条件下系统动力响应的敏感性分析,得到了全局敏感性系数及输入参数的重要度排序,此外,还采用K-S测度敏感性分析法对结果进行了检验。分析表明:燃料组件地震响应对2个部位的接触刚度变化较敏感,3个部位切向载荷极值均对所在部位接触刚度的变化最敏感。相关方法与分析流程可推广至反应堆冷却剂系统及其他主设备,为优化设计参数的选取提供定量分析手段与数据支持。The analysis of the sensitivity of the input parameters to the dynamic responses of the reactor system is an important prerequisite for optimal design.In this paper,the contact stiffness and clearance of the key parts of the reactor system are taken as input variables,and the Sobol’s method is used to analyze the sensitivity of the key input parameters to the dynamic response of the system under the seismic condition.The global sensitivity coefficient and the order of importance of the input parameters are obtained.The results were also tested using the K-S measure sensitivity analysis method.The analysis shows that the seismic response of the fuel assembly is sensitive to the change of the contact stiffness at two locations,and the tangential load extreme value is most sensitive to the change of the contact stiffness at the location.The relevant methods and analysis processes can be extended to the reactor coolant system and other main equipment to provide the method for quantitative analysis and data support for the selection of optimized design parameters.

关 键 词：反应堆系统 地震响应 敏感性分析 优化设计 

分 类 号：O322[理学—一般力学与力学基础]