大型蒸汽发生器中湍流的数据同化:第一部分--基于卡尔曼滤波器的迭代集合重构

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Sen Li , Yuheng Lu , Chuangxin He , Chunjing Song , Yingzheng Liu , Yun Zhong
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引用次数: 0

摘要

本研究的重点是利用基于集合卡尔曼滤波器(EnKF)的迭代数据同化(DA)技术,再现大型蒸汽发生器(SG)系统内的全局湍流平均值。在考虑 U 型阵列的体积流量再分布的同时,引入了压缩定向损失模型以降低计算成本。结果表明,DA 方法通过拓宽射流核心、增强射流阵列穿透力和减小湍流分离气泡尺寸,改进了预测结果,与实验数据更加吻合。反应堆冷却剂泵(RCP)入口处的入口速度曲线也得到了准确的体现。优化模型的可扩展性在 RCP 出口处得到了验证。DA 模型更准确地捕捉了流体动力学,包括加速、减速和突然膨胀区域的垂直运动,从而更好地估算了总压力损失。这些改进为 DA 方法在实际工程设计和运行中的应用提供了可能性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction
This research focuses on reproducing the global turbulent mean flow within a large-scale steam generator (SG) system using an iterative Ensemble Kalman Filter (EnKF)-based data assimilation (DA). A compressed directional loss model is introduced to reduce computational costs while considering volume flow rate redistribution across the U-shaped arrays. Results demonstrate that the DA approach improves predictions, showing better agreement with experimental data by widening the jet core, enhancing jet array penetration, and reducing turbulent separation bubble size. The inlet velocity profile at the reactor coolant pump (RCP) entrance is also accurately represented. The extensibility of the optimized model is validated at the RCP outlet. The DA model more accurately captures fluid dynamics, including acceleration, deceleration, and vertical movement in the sudden expansion region, leading to better estimations of total pressure loss. These improvements open up possibilities of DA approach for real engineering applications in both design and operation.
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来源期刊
Annals of Nuclear Energy
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.
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