三代核电厂C型管束热交换器模拟体的动态特性分析和试验研究

摘要

非能动余热排出热交换器(PRHR HX)是三代核电厂特有的安全级设备.与传统的换热器不同,该热交换器通过支撑条的形式来支撑C型传热管,以保证设备在操作和地震工况下的安全运行.在动态分析中,对于大量的C型管必须在模型中予以简化,其中C型管和支撑条间存有空隙,形成非线性接触问题,是动态特性分析中的难点.通过非能动余热排出热交换器模拟体试验件的模态分析和试验结果对比,获得简化等效C型管的动态特性分析方法,该分析和试验结果可直接应用于类似热交换器的抗震分析和评定.%Passive residual heat removal heat exchanger(PRHR HX) is one of the new safety designs in the third generation nuclear power plants.Unlike conventional heat exchangers,the PRHR HX uses supporting rods to keep the tube bundles,shaped like the letter "C",from excessive motion during operation and during seismic events.Since gaps exist between the rods and the tubes,the dynamic characteristics of the rods-tubes assembly is a very complex non-linear problem.To investigate the dynamic characteristics and the seismic capabilities of the PRHR HX,a simplified structure simulating the PRHR HX was manufactured and tested.By comparing with the modal results from the tests,we were able to determine how to model the rod-tube contact conditions and how to simplify the huge number of tubes and rods in the finite element modeling.