Research on fluid flow and heat transfer characteristics in a three-dimensional condenser

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-10-09 DOI:10.1016/j.anucene.2024.110967

Zhiqiang Duan, Yuan Tian, Siyuan Wang, Ling Long, Jianjun Deng

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Abstract

The condenser plays a crucial role in nuclear power plants, impacting equipment economics and safety through shell-side two-phase flow and heat transfer. However, existing research has oversimplified the tube bundles, lacking comprehensive information for optimal performance. In this research, a three-dimensional method incorporating mixture and multiphase flow condensation models was used to investigate flow behavior and heat transfer characteristics without simplifying the internal structure. Calculation details were enhanced by omitting the porous medium approach. The numerical model achieved reasonable accuracy when compared to theoretical calculations for a range of steam mass flow rates. Analysis of numerical results, including pressure, velocity, temperature, air mass fraction, and heat transfer coefficient, revealed that steam flow rate and air mass fraction were key factors influencing heat transfer. This research demonstrates the method’s capability to capture intricate calculation details, providing valuable insights for optimization design considerations in condenser performance.

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三维冷凝器中的流体流动和传热特性研究

冷凝器在核电站中起着至关重要的作用，通过壳侧两相流动和热传递影响设备的经济性和安全性。然而，现有研究过于简化管束，缺乏实现最佳性能的全面信息。在这项研究中，采用了一种包含混合物和多相流冷凝模型的三维方法，在不简化内部结构的情况下研究流动行为和传热特性。由于省略了多孔介质方法，计算细节得到了加强。在蒸汽质量流量范围内，数值模型与理论计算结果相比达到了合理的精度。对压力、速度、温度、空气质量分数和传热系数等数值结果的分析表明，蒸汽流速和空气质量分数是影响传热的关键因素。这项研究表明，该方法能够捕捉到复杂的计算细节，为冷凝器性能的优化设计提供有价值的见解。

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.