Reynolds应力输运模型中紊流热流的代数实现及跨管束的模拟

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Han Liu , Hao Sun , Binghuo Yan , Jun Chen , Zhikang Lin
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引用次数: 0

摘要

铅铋共晶(LBE)具有高沸点和高导热性,是一种优良的快堆冷却剂。湍流换热是一个复杂的现象,LBE的数值换热受到其极低的普朗特数的限制。传统的雷诺类比法不能准确地描述能量方程中的湍流热流密度。因此,本文将代数湍流热流模型应用于CFD程序中的雷诺应力输运(RST)模型。利用直接数值模拟(DNS)数据验证了该模型的准确性。利用该模型对LBE交叉管束的流动传热进行了预测,并拟合出传热相关性。讨论了该模型在核工业中的潜在应用。为液态金属冷却快堆的设计和安全性分析提供了一种新的数值方法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Implementation of algebraic turbulent heat flux into Reynolds stress transport model and simulation of crossing tube bundles
Lead bismuth eutectic (LBE) is an excellent coolant for fast reactors, owing to its high boiling point and high thermal conductivity. Turbulent heat transfer is a complex phenomenon, and the numerical heat transfer of LBE is constrained by its extremely low Prandtl number. Conventional Reynolds analogy method fails to exactly describe the turbulent heat flux (THF) in the energy equation. Therefore, this paper implements the algebraic turbulent heat flux model into the Reynolds stress transport (RST) model within CFD program. The accuracy of this model was verified using direct numerical simulation (DNS) data. Furthermore, the model was employed to predict the flow heat transfer of LBE cross tube bundles, from which a heat transfer correlation was fitted. The potential application of this model in the nuclear industry is discussed. This work provides a new numerical method for the design and safety analysis of liquid metal-cooled fast reactors.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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