摘要
管道是核电站中的重要部件。为了使管道满足规范要求,需要对管道进行应力分析与评定。本文分析了二代改进型核电站1级和2级管道应力分析与评定过程,论述了不同载荷下管道应力的计算方法,并分析了RCC-M规范版本的变化对管道应力分析结果的影响。最后,以岭澳核电站二期工程安全注入系统为例,对管道进行了应力分析与评定,满足了RCC-M规范的设计要求,并输出了支撑载荷、接管载荷、管道位移等接口参数。本文可以为二代改进型核电站管道系统应力分析与评定提供帮助。
Background: Piping is an important part in nuclear power plants. Purpose: In order to make piping meet the specification requirements, it is necessary to analyze and evaluate piping stress. Methods: This paper deals with the stress analysis and evaluation of the class 1 and class 2 piping of improved second-generation nuclear power plants, and discusses the calculation methods of piping stress due to various loads. Also, the effects of changing the RCC-M code edition on the calculation of piping stress are summarized. Results: Taking the LingAo Nuclear Power Plant Phase II engineering safety injection system as an example, the piping stress analysis and evaluation are performed, and the results meet the RcC-M code requirements. Besides, the interface parameters including the support loads, nozzle loads, displacements of the piping and so on are obtained. Conclusions: This paper will provide technical support for stress analysis and evaluation of improved second-generation nuclear power plant piping systems.
出处
《核技术》
CAS
CSCD
北大核心
2013年第4期59-63,共5页
Nuclear Techniques
基金
国家科技重大专项核级管道设计技术课题(2011ZX06004-004)资助