Influence of internal heat generation on turbulent heat transfer in a pipe flow with wall cooling

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Dong-Hyuk Park, Bum-Jin Chung
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引用次数: 0

Abstract

We investigated the influence of internal heat generation on turbulent heat transfer in a pipe flow, aiming at application to the heat exchangers of Molten Salt Reactors (MSRs), where nuclear fuel is dissolved in the coolant. The non-homogeneous energy equation arising from the internal heat source was solved using the superposition principle and calculations were conducted from the entrance region to the fully developed region. Local and mean Nusselt numbers (Nu) were evaluated, varying Reynolds numbers (Re = 5 × 103–10⁶), Prandtl numbers (Pr = 1–10), and internal heat generation parameters (Ω = 1–103). Results show that the internal heat generation enhances the heat transfer rate. This enhancement increases with higher Ω and lower Re and Pr. However, due to the thin viscous sublayer in turbulent flow, the maximum local Nu enhancement remained below 12 %. Flow regime where internal heat generation produces a significant impact were identified, and a correction factor was developed. This study provides fundamental insights into the influence of internal heat generation and offers a quantitative basis for the design of MSR heat exchangers.
管内产热对壁面冷却管内湍流换热的影响
我们研究了管内热产生对管内湍流传热的影响,旨在将其应用于核燃料溶解在冷却剂中的熔盐堆(MSRs)热交换器。利用叠加原理求解了由内热源引起的非齐次能量方程,并从入口区到完全发达区进行了计算。评估局部和平均努塞尔数(Nu)、不同雷诺数(Re = 5 × 103-10 26)、普朗特数(Pr = 1-10)和内部产热参数(Ω = 1-103)。结果表明,内部产热提高了传热速率。随着Ω的升高和Re、Pr的降低,Nu的增强增大,但由于湍流中存在较薄的粘性亚层,局部Nu的最大增强保持在12%以下。确定了内部热产生产生重大影响的流动状态,并开发了校正因子。本研究对内部产热的影响提供了基本的认识,并为MSR换热器的设计提供了定量的依据。
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
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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