Experimental and numerical research of thermo-hydraulic characteristics of liquid lead–bismuth eutectic and S-CO2 in a MCHE

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.2025.111879

Hong Liu , Zhigang Zhang , Shuo Yang , Guangliang Chen , Zhibin Rao , Runze Wang

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引用次数: 0

Abstract

This study utilized experimental methods to investigate the variation of the overall heat transfer coefficient in a microchannel heat exchanger (MCHE) with the Reynolds numbers of liquid lead–bismuth eutectic (LBE) and supercritical carbon dioxide (S-CO₂). Additionally, we obtained numerical values for the resistance of liquid LBE and S-CO₂ with respect to their respective Reynolds numbers. Furthermore, we employed numerical simulation methods to analyze the thermal hydraulics characteristics of LBE and S-CO₂ within the MCHE. We found that the numerical simulation results were in good agreement with the experimental data. Using the numerical results, we further analyzed the variations of the mainstream temperature, wall temperature, and heat flux density for both fluids. We also investigated the influence of fluid velocities and heat exchanger spacing on heat transfer. Finally, we proposed correlation equations for the calculation of heat transfer and resistance for LBE and S-CO₂.

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MCHE中液态铅铋共晶和S-CO2热水力特性的实验与数值研究

采用实验方法研究了液态铅铋共晶（LBE）和超临界二氧化碳（S-CO2）雷诺数对微通道换热器（MCHE）总换热系数的影响。此外，我们还获得了液态LBE和S-CO2相对于各自雷诺数的阻力数值。此外，采用数值模拟方法分析了MCHE内LBE和S-CO2的热工特性。结果表明，数值模拟结果与实验数据吻合较好。利用数值结果，进一步分析了两种流体的主流温度、壁面温度和热流密度的变化规律。研究了流体流速和换热器间距对换热的影响。最后，我们提出了LBE和S-CO2传热和阻力计算的相关方程。

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.