反应堆堆内构件声致压力脉动分析及应用  

Investigation on the Acoustic Pressure Pulsation Analysis and Application of Reactor Internals

作　　者：艾卫江 AI Wei-jiang(Shanghai Nuclear Engineering Research and Design Institute,Shanghai 200233)

机构地区：[1]上海核工程研究设计院有限公司,上海200233

出　　处：《现代计算机》2021年第7期4-7,共4页Modern Computer

基　　金：国家科技重大专项:反应堆冷却剂系统稀疏波与压力脉动载荷分析软件开发(No.2019ZX06004006)。

摘　　要：反应堆堆内构件是核电厂的关键设备,用于支承堆芯,主要失效模式是振动疲劳。国和一号堆内构件需根据RG1.20完成振动综合评价。RG 1.202007版新增声致振动影响的评估要求。堆内构件的声致振动载荷来自主冷却剂泵的周期性转动。目前,国外仅西屋公司开发计算程序,国内尚无计算软件。通过声学控制方程简化,开发声致压力脉动有限差分求解程序,经理论解验证,计算堆内构件声致压力脉动载荷,并以堆内测量格架组件为例,应用于堆内构件的声致振动分析,可有力支持堆内构件的应力评定。The Reactor Internals,which are used to support the fuel assembly,play a very important role in the nuclear power station.The main failure mode of the Reactor Internals is fatigue induced by vibration.The CAP1400 Reactor Internals should perform comprehensive vibration evaluation following RG 1.20.The 2007 edition of RG 1.20 adds the assessment requirement of acoustic induced vibration.The acoustic vi⁃bration load of Reactor Internals comes from the periodic rotation of Reactor Coolant Pump.The only calculation program before was devel⁃oped by Westinghouse company in America.This article developed the acoustic pressure pulsation finite difference solution program based on the simplification of acoustic theoretical control equations.This program was benchmarked by theoretical solution,and was used to cal⁃culate the acoustic pressure pulsation load through the reactor coolant system.These loads were then applied on the finite element model to calculate the acoustic induced vibration of Reactor Internals(takes the Instrument Grid Assembly as an example),which can support the fi⁃nal high-cycle fatigue evaluation.

关 键 词：堆内构件 声致压力脉动 谐响应 有限差分 

分 类 号：TM623[电气工程—电力系统及自动化]