节点文献
压力容器堆芯筒体应力强度可靠性研究
Research on reliability of stress strength of pressure vessel core cylinder
【作者】 刘贞谷; 姜露; 庾明达; 李丽娟; 田俊; 张丽屏; 张毅雄;
【Author】 LIU Zhen-yu;JIANG Lu;YU Ming-da;LI Li-juan;TIAN Jun;ZHANG Li-ping;ZHANG Yi-xiong;National Key Laboratory of Science and Technology on Reactor System Design Technology;Nuclear Power Institute of China;
【机构】 核反应堆系统设计技术重点实验室; 中国核动力研究设计院;
【摘要】 本文将各输入参数的随机性概念引入到核设备的设计中,开展基于概率论的可靠性分析设计,考虑了参数的随机波动及不确定性,计算结构的可靠度以及结构对设计参数的敏感性,从而为结构设计提供更多的反馈信息和指导意见。本文对常用的几种应力强度可靠性分析技术进行了研究,分析了各自的优缺点,以压力容器堆芯段筒体为例,采用解析法、Ansys、OPTIMUS对其可靠度进行了计算,验证了可靠性分析方法及技术在核级设备分析评价的可行性。
【Abstract】 In this paper,the randomness concept of each input parameter is introduced into the design of nuclear equipment,and the reliability analysis design based on probability theory is carried out.The stochastic fluctuation and uncertainty of parameters are considered,as well as the reliability of the calculated structure and the sensitivity of the structure to the design parameters.In addition,the calculation can provide more feedback and guidance for structural design.In this paper,several commonly used stress intensity reliability analysis techniques are studied,and their advantages and disadvantages are analyzed.Taking the pressure vessel core section cylinder as an example,the reliability is calculated by analytical method,Ansys and OPTIMUS.The feasibility of the reliability analysis method and technology in the analysis and evaluation of nuclear equipment is verified.
【Key words】 stress intensity; reliability; nuclear equipment; sensitivity; pressure vessel;
- 【会议录名称】 中国核科学技术进展报告(第六卷)——中国核学会2019年学术年会论文集第7册(计算物理分卷、核物理分卷、粒子加速器分卷、核聚变与等离子体物理分卷、脉冲功率技术及其应用分卷、辐射物理分卷、核工程力学分卷、核测试与分析分卷)
- 【会议名称】中国核学会2019年学术年会
- 【会议时间】2019-08-20
- 【会议地点】中国内蒙古包头
- 【分类号】TL351.6
- 【主办单位】中国核学会