Preliminary exploration of liquid metals turbulent heat flux model based on OpenFOAM solver: Second-order differential heat flux model

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-10-15 DOI:10.1016/j.anucene.2024.110969
Yuefeng Guo , Xingkang Su , Guan Wang , Long Gu , Xianwen Li
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Abstract

Liquid metal-cooled fast reactors use liquid metals such as lead–bismuth eutectic (LBE) and sodium as the coolant, and the thermo-hydraulic characteristics of liquid metals have a large effect on the thermodynamic parameters of the reactor core. The problem is that using the traditional constant turbulent Prandtl number Prt of 0.85 ∼ 0.9, which is generally derived from the Reynolds analogy hypothesis suitable for conventional fluids, will greatly affect the accuracy of the numerical prediction of the thermal–hydraulic properties of liquid metals. In order to obtain more accurate liquid LBE and sodium turbulent heat transfer data, this research introduces a second-order differential heat flux model (DHFM) based on the open-source computational fluid dynamics platform OpenFOAM. The turbulent heat flux model is also tested with geometrical model of a pipe flow, the square and triangular bundle flow. It is shown that the calculation of Nusselt number Nu for liquid LBE by the second-order differential heat flux model (DHFM) is larger than the correlations in the square and triangular bundle flow. While the calculated Nu for liquid sodium is smaller than the correlations in the square and triangular bundle flow. Among them, the calculated results of liquid LBE and sodium in the pipe flow are in good agreement with the experimental data and the correlations. The DHFM model has a larger error in the square and triangular bundle channels for liquid LBE and sodium. In addition, the non-dimensional temperature, temperature fluctuation and dissipation characteristics of different geometrical models are also investigated in this research. This research can serve as a reference for the numerical calculation of turbulent heat transfer in liquid metals. It also enriches the study of thermal-hydraulics in liquid metal reactors.
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基于 OpenFOAM 求解器的液态金属湍流热通量模型初探:二阶微分热通量模型
液态金属冷却快堆使用铅铋共晶(LBE)和钠等液态金属作为冷却剂,液态金属的热液特性对堆芯的热力学参数有很大影响。问题在于,使用传统的恒定湍流普朗特数 Prt 0.85 ∼ 0.9(一般由雷诺类比假设得出,适用于常规流体)将极大地影响液态金属热液特性数值预测的准确性。为了获得更精确的液体 LBE 和钠湍流传热数据,本研究引入了基于开源计算流体力学平台 OpenFOAM 的二阶微分热通量模型(DHFM)。该湍流热通量模型还通过管道流、正方形和三角形束流的几何模型进行了测试。结果表明,通过二阶微分热通量模型(DHFM)计算出的液体 LBE 的努塞尔特数 Nu 要大于方形和三角形束流中的相关系数。而液体钠的计算 Nu 小于方形和三角形束流中的相关系数。其中,液态 LBE 和钠在管道流中的计算结果与实验数据和相关系数吻合较好。DHFM 模型在液体 LBE 和钠的方形和三角形束流通道中误差较大。此外,本研究还考察了不同几何模型的非尺寸温度、温度波动和耗散特性。该研究可为液态金属中的湍流传热数值计算提供参考。它还丰富了液态金属反应器中的热-水力学研究。
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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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