Study of operational stability on reactor coolant pump with staggered guide vane under coast-down condition

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-06-12 DOI:10.1016/j.nucengdes.2025.114227

Daoxing Ye , Rui Deng , Junlin Chen , Junyu Zhang , Jiaming Han , Mengke Wu , Binhao Liu

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Abstract

To explore the impact of staggered guide vane on operational stability of reactor coolant pump during coast-down condition, numerical methods were employed to study the reactor coolant pump equipped with staggered guide vane. Research shows that during the entire coast-down process, staggered guide vane can significantly reduce the pressure pulsation of impeller at impeller rotational frequency and blade passing frequency; decreasing the amplitude of pressure pulsation in volute and guide vanes, making the intensity distribution of pressure pulsation more uniform. However, in the later stages of coast-down, due to the deterioration in the match between impeller and vane, these improvements diminish. Staggered guide vane can make the radial force distribution more uniform and reduce the radial force amplitude at the impeller rotational frequency, but this improvement decreases from 14.2% to 7.2% as coast-down progresses.

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滑倒条件下交错导叶反应堆冷却剂泵运行稳定性研究

为了探索交错导叶对反应堆冷却剂泵在平稳状态下运行稳定性的影响，采用数值方法对装有交错导叶的反应堆冷却剂泵进行了研究。研究表明，在整个降速过程中，交错导叶可以显著降低叶轮在叶轮转动频率和叶片通过频率下的压力脉动；减小蜗壳和导叶内压力脉动幅值，使压力脉动强度分布更加均匀。然而，在滑行的后期阶段，由于叶轮和叶片之间匹配的恶化，这些改进减少了。交错导叶可以使径向力分布更加均匀，降低叶轮旋转频率处的径向力幅值，但随着顺滑的进行，改善幅度从14.2%下降到7.2%。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.