核安全2023，Vol.22Issue(6)：73-79,7.
美国小型模块化压水堆堆内构件流致振动分析方法研究
Research on Flow Induced Vibration Analysis Method for Internal Components of Small Modular Pressurized Water Reactor in the United States
刘锐 1孙树海 1刘宇生 1吴彦农1
作者信息
- 1. 生态环境部核与辐射安全中心,北京 100082
- 折叠
摘要
Abstract
In order to evaluate the comprehensive vibration behavior of small modular reactor(SMR)internal components and demonstrate that the internal components have sufficient safety margin under the influence of flow induced vibration,the US Nuclear Regulatory Commission(NRC)released the 4th edition of R.G.1.20,"Outline for Comprehensive Evaluation of Internal Component Vibration during Pre operation and Initial Startup Testing,"in 2017.The special requirements of the 4th edition R.G.1.20 for the comprehensive vibration evaluation of small modular reactor internals were studied,including the special requirements for the scope of comprehensive vibration evaluation,the special requirements to be considered for the control rod drive system,and the main pump.We investigated the analysis and evaluation methods of flow induced vibration in small reactor NuScale internal components in the United States,and analyzed the potential excitation mechanisms that may affect the vibration of small modular pressurized water reactor internal components.This provides a reference for the evaluation of flow induced vibration in small modular pressurized water reactor internal components in China.关键词
小型模块化反应堆(SMR)/堆内构件/流致振动/R.G.1.20Key words
Small Modular Reactor(SMR)/Internal components/flow induced vibration/R.G.1.20分类
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刘锐,孙树海,刘宇生,吴彦农..美国小型模块化压水堆堆内构件流致振动分析方法研究[J].核安全,2023,22(6):73-79,7.
