Reliability analysis of impeller and shaft system in shaft-sealed reactor coolant pump

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-18 DOI:10.1016/j.anucene.2025.111884

Long Cai , Zhe Jiao , Dongbo Qi , Xuezhi Ding , Yuan Xu , Yun Long

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Abstract

This study addresses the reliability issues of the axial seal main pump (RCP) impeller and shaft system under high-temperature and high-pressure water conditions. It employs fluid–structure interaction (FSI) theory and modal analysis to conduct a systematic study of dynamic characteristics and fatigue life. Using FSI simulation model, this study compares the natural frequency variations under dry and wet modal conditions to reveal the influence of added water mass on structural dynamics. Transient dynamic stress calculations are completed on the ANSYS Workbench platform. The fatigue life of the impeller is predicted using Miner’s linear cumulative damage theory and nCode DesignLife software. The results indicate that most regions of the impeller have a lifespan exceeding 7.223 × 10¹⁰ cycles (approximately 92.5 years). Localized fatigue risks are identified only at the blade roots. Campbell diagram analysis shows that the rated speed of the nuclear main pump avoids the main resonant critical speeds, but attention should be paid to the influence of low-frequency excitation on stability. The findings of this study provide a theoretical basis for the structural optimization and reliability enhancement of nuclear main pumps.

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轴封式反应堆冷却剂泵叶轮及轴系可靠性分析

研究了高温高压水工况下轴封主泵（RCP）叶轮和轴系的可靠性问题。采用流固耦合理论和模态分析方法对其动力特性和疲劳寿命进行了系统的研究。利用FSI模拟模型，比较了干、湿两种模态条件下的固有频率变化，揭示了加入水量对结构动力学的影响。在ANSYS Workbench平台上完成瞬态动应力计算。利用Miner的线性累积损伤理论和nCode DesignLife软件对叶轮的疲劳寿命进行了预测。结果表明，叶轮大部分区域的寿命超过7.223 × 1010个循环（约92.5年）。局部疲劳风险仅在叶片根部确定。坎贝尔图分析表明，核主泵的额定转速避免了主共振临界转速，但应注意低频激励对稳定性的影响。研究结果为核主泵结构优化和可靠性提高提供了理论依据。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.