核主泵压力脉动及其诱导振动研究进展  

Pressure Pulsation and Its Induced Vibration of Main Coolant Pumps in Nuclear Power Plant

作　　者：雷明凯[1] 陈语曦 朱宝[1] 胡兴成 LEI Ming-kai;CHEN Yu-xi;ZHU Bao;HU Xing-cheng(Dalian University of Technology,Dalian,Liaoning Prov.116024,China)

机构地区：[1]大连理工大学

出　　处：《中国核电》2019年第3期275-279,共5页China Nuclear Power

基　　金：国家重点基础研究发展计划项目“大功率屏蔽式核主泵自主化形性协同制造原理”(2015CB057300)资助

摘　　要：文章综述了近十年来我国大功率核主泵工质流动结构、特别是非定常流动特性与压力脉动之间的关系,以及压力脉动诱发振动方面所取得的研究结果。主要总结了核主泵常规压力脉动和异常压力脉动行为、压力脉动产生的微观机制、压力脉动对振动影响及其抑制方法等研究进展。通过核主泵模型试验结合最新发展的流体动力学数值模拟计算,描述了叶轮与导叶间动静干涉的物理过程,确定了设计的正常工况、异常工况、制造特征参数的影响作用。揭示了压力脉动与振动的相干规律,提出了减少和抑制核主泵压力脉动诱导振动的有效措施。This paper reviews the research and development of fluid structure in the main coolant pumps,especially the unsteady flow and pressure pulsation,and its induced vibration in recent 10 years in China.The normal and abnormal pressure pulsation behavior,physical mechanism of generation,and correspondent pulsation-induced vibration and its suppression methods are comprehensively summarized.The process of rotor-stator intervene is described based on the experimental investigation of model pumps and newly developed numerical calculation of fluid dynamics.The normal and abnormal working conditions designed and characteristic parameters of manufacturing are determined.The coherence analysis between pressure pulsation and vibration is performed to reduce and suppress the pulsation-induced vibration in the main coolant pumps.

关 键 词：核主泵 压力脉动 诱导振动 流体动力学 表/界面完整性 

分 类 号：TM623[电气工程—电力系统及自动化]