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轴流式核主泵内部流动特性数值计算与试验

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以轴流式核主泵为研究对象,采用数值模拟和试验验证相结合的方法,计算模型为SSTk-ω湍流模型,重点选取了 0。9Q,1。0Q与1。1Q工况,对轴流式核主泵内部流动特性进行分析,结合性能试验台完成试验验证。在分析计算结果时,重点考察了泵出口中心截面的速度流线图和速度分布云图,以此来深入探讨泵在不同流量条件下内部流动模式的差异及其演变趋势;提取叶轮与导叶叶片通道回转面的压力速度云图、叶轮叶片与导叶叶片的压力载荷曲线,对比分析不同流量下泵内部流动结构及其变化规律,进一步揭示叶轮和导叶内的流动分布及能量转换机制。通过试验对数值计算开展了对比验证,计算结果与试验结果基本吻合,扬程模拟值比试验值低3。87%,效率模拟值比试验值低1。94%。本研究深入揭示了轴流式核主泵内部流动特性,对充分认识核主泵水力结构与内部流动关联性至关重要,为轴流式核主泵的设计和性能优化提供参考依据。
Numerical simulation and experiment on internal flow characteristics of axial-flow nuclear reactor coolant pump
An axial-flow nuclear reactor coolant pump was taken as the research object,and a method of employing a combination of numerical calculation and experimental research was adopted.The SST k-ω turbulence model was used,and 0.9Q,1.OQ,and 1.1Q were selected as working conditions to analyze the internal flow characteristics of the axial-flow nuclear reactor coolant pump.The experimental verification was completed on the comprehensive performance test bench of the pump.When analyzing the calculation results,the velocity streamline diagram and velocity distribution cloud diagram of the center section of the pump outlet were examined in detail to explore the differences in the internal flow patterns and their evolution trends of the pump under different flow conditions.The pressure-velocity cloud diagrams of the rotating surfaces of the impeller and guide vane blade channels,and the blade pressure-load curves of the impeller blades and guide vane blades were ex-tracted,and the internal flow structure and its changing law of the pump under different flow rates were compared and analyzed to further reveal the flow distribution and energy conversion mechanism inside the impeller and guide vanes.The numerical calculation was compared and verified through experi-ments.The calculated results are basically consistent with the experimental results.The head simulation value is 3.87%lower than the experimental value,and the efficiency simulation value is 1.94%lower than the experimental value.This research work deeply reveals the internal flow characteristics of the axial-flow nuclear reactor coolant pump,which is very important to fully understand the correlation be-tween the hydraulic structure and internal flow of the nuclear reactor coolant pump,and provides a reference for the design and performance optimization of the axial-flow nuclear reactor coolant pump.

axial-flow nuclear reactor coolant pumpinternal flow characteristicsnumerical simulation and experimentturbulence model

蔡龙、徐源、龙云、周震、朱荣生、袁寿其

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哈尔滨电气动力装备有限公司,黑龙江哈尔滨 150060

大连理工大学材料科学与工程学院,辽宁大连 116024

江苏大学国家水泵及系统工程技术研究中心,江苏镇江 212013

轴流式核主泵 内部流动特性 数值计算与试验 湍流模型

2024

排灌机械工程学报
中国农业机械学会排灌机械分会,江苏大学流体机械工程技术研究中心

排灌机械工程学报

CSTPCD北大核心
影响因子:1.055
ISSN:1674-8530
年,卷(期):2024.42(12)