二代改进型核电站管道系统应力分析与评定

Stress analysis and evaluation of improved second-generation nuclear power plant piping systems

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.