300MW级核电站主泵压力脉动研究  

Study on Pressure Fluctuation in Main Pump of 300 MW Nuclear Power Plants

作　　者：陈向阳[1] 袁丹青[1] 杨敏官[1] 袁寿其[1] 

机构地区：[1]江苏大学,江苏镇江212013

出　　处：《核动力工程》2010年第3期78-82,共5页Nuclear Power Engineering

摘　　要：以国内某300 MW级核电站主泵为对象,利用Navier-Stokes方程和标准k-ε湍流模型对其内部流场进行了非定常数值模拟,并根据模拟结果对主泵叶轮进、出口和导叶出口处的压力脉动进行研究分析。结果表明:整个泵段的脉动频率主要受叶轮转动频率影响,对于叶轮段为球型的主泵,最大脉动幅值由叶轮入口前向导叶体不断减小,且沿叶高方向依次增大;在叶轮轮缘附近,由于受到球型泵壳的影响,脉动幅值出现减小。From the safety of reactor coolant pump,the numerical investigation of internal unsteady flow in reactor coolant pump of one 300MW nuclear power plant in China that is based on the calculation Navier-Stokes equation and standard k-ε turbulence model is carried out in this paper.Through the analysis of pressure fluctuation which locates at impeller,guide vane and inlet parts,it is concluded that the frequency of pressure fluctuation in the reactor coolant pump is exclusively governed by the blade-passing frequency.For the spherical shell pump,the maximum amplitude of pressure fluctuation decreases from inlet to guide vane but increases from hub to impeller edge except for the vicinity of impeller edge in the impeller part which follows the former mode.The comprehensive analysis of maximum amplitude of pressure fluctuation shows that the hydraulic parts could reduce the effects of pressure fluctuation,increase only a few vibrations to the whole unit and these are in favor of improving the safety performance of main pump unit.

关 键 词：反应堆冷却剂泵 安全性 压力脉动 优化设计 

分 类 号：TH314[机械工程—机械制造及自动化]