Subcooled flow boiling in a horizontal circular pipe under high heat flux and high mass flux conditions

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-13 DOI:10.1016/j.anucene.2024.111030
Deepak K. Solanki , Kausik Nandi , Joe Mohan , Arunkumar Sridharan , S.V. Prabhu
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Abstract

Subcooled flow boiling of water is widely observed in high heat flux and high mass flux (HHHM) cooling applications such as heat exchangers, refrigeration equipment, boiler tubes and nuclear reactor core fuel channels in pressurized heavy water reactors (PHWR). In this study, the focus is on investigating the local heat transfer coefficient (HTC) and pressure drop in a horizontal tube experiencing subcooled boiling of water under low pressure and HHHM conditions. The study encompasses different geometrical parameters such as tube diameter (5.5 mm, 7.5 mm, 9.5 mm and 12 mm) and length (550 mm for each of the tubes). The operating parameters that are varied include mass flux (248–2000 kg/m2.s) and heat flux (0–1837 kW/m2). Infrared thermography is used to measure the local wall temperature. A non-dimensional correlation for the diabatic pressure drop ratio (ratio of diabatic pressure drop to adiabatic pressure drop) as a function of Jakob number (Ja), Boiling number (Bo) and diameter ratio is developed. Subcooled boiling pressure drop ratio for 5.5 mm, 7.5 mm and 9.4 mm diameter tubes is 2.23 which is independent of diameter. A correlation for the two phase local HTC during subcooled flow boiling conditions as a function of Ja, Bo and Prandtl number (Pr) is also developed.
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高热通量和高质通量条件下水平圆管中的过冷流沸腾
在高热通量和高质量通量(HHHM)冷却应用中,如热交换器、制冷设备、锅炉管道和压水重水反应堆(PHWR)中的核反应堆堆芯燃料通道,广泛存在水的过冷流动沸腾现象。在本研究中,重点是研究在低压和 HHHM 条件下,水平管内水过冷沸腾时的局部传热系数(HTC)和压降。研究包括不同的几何参数,如管子直径(5.5 毫米、7.5 毫米、9.5 毫米和 12 毫米)和长度(每根管子 550 毫米)。不同的运行参数包括质量通量(248-2000 kg/m2.s)和热通量(0-1837 kW/m2)。红外热成像技术用于测量局部管壁温度。得出了绝热压降比(绝热压降与绝热压降之比)与雅各布数 (Ja)、沸腾数 (Bo) 和直径比之间的非尺寸相关关系。直径为 5.5 毫米、7.5 毫米和 9.4 毫米的管道的过冷沸腾压降比为 2.23,与直径无关。此外,还得出了过冷流动沸腾条件下两相局部 HTC 与 Ja、Bo 和 Prandtl 数 (Pr) 的函数关系。
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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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