Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-10-29 DOI:10.1016/j.anucene.2024.111011

Long Yun, Xu Yuan, Guo Xi’an, Zhang Mingyu

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Abstract

This paper presents a study on the internal flow characteristics of reactor coolant pumps using Dynamic Mode Decomposition (DMD) technology. As a core component of nuclear power plants, the internal flow characteristics of reactor coolant pumps play a crucial role in the performance and stability of the pumps. This paper initially introduces the application of DMD and Proper Orthogonal Decomposition (POD) methods in fluid mechanics, emphasizing the effectiveness of DMD in analyzing the dynamic characteristics of flow fields. A computational model of the reactor coolant pump was constructed, and numerical simulation of the internal flow field under non-uniform inflow conditions was conducted. The impact of the lower chamber of the steam generator on the pump’s inlet conditions was evaluated. The numerical simulation results were analyzed using DMD technology, extracting flow characteristics and revealing the main flow modes and dynamic behaviors in the flow field. The results demonstrate that the DMD technology can accurately capture the time-dynamic characteristics within the flow field, providing crucial insights for optimizing performance and preventing faults in the reactor coolant pump.

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基于 DMD 的反应堆冷却剂泵内流激励特性分析

本文利用动态模式分解（DMD）技术对反应堆冷却剂泵的内部流动特性进行了研究。作为核电站的核心部件，反应堆冷却剂泵的内部流动特性对其性能和稳定性起着至关重要的作用。本文首先介绍了 DMD 和适当正交分解（POD）方法在流体力学中的应用，强调了 DMD 在分析流场动态特性方面的有效性。本文构建了反应堆冷却剂泵的计算模型，并对非均匀流入条件下的内部流场进行了数值模拟。评估了蒸汽发生器下腔对泵入口条件的影响。利用 DMD 技术对数值模拟结果进行了分析，提取了流动特征，揭示了流场中的主要流动模式和动态行为。结果表明，DMD 技术能够准确捕捉流场中的时间-动态特性，为优化反应堆冷却剂泵的性能和预防故障提供重要见解。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.