Performance analysis of Dowtherm A heat pipe with internal vapor monitoring

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mitchell Stephenson , Trevor Melsheimer , Joseph Seo , Abdulbasit Aloufi , Hansol Kim , Yassin A. Hassan
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Abstract

Medium-temperature heat pipes, operating in the 200–600 °C range, find widespread application in sectors such as nuclear microreactors, solar energy collectors, thermal energy storage, and space. Efficient, passive heat transfer devices, like heat pipes, are essential for power systems operating in this temperature range. Despite such a broad range, traditional working fluids for heat pipes in the medium-temperature regime frequently underperform, prompting the need for more research into these working fluids. Dowtherm A is attractive for its chemical compatibility with heat pipe materials, low toxicity, low flammability, and adequate thermal–hydraulic properties, things that cannot be said for most medium-temperature heat pipe working fluids. This experimental study investigates the performance of Dowtherm A as a medium-temperature heat pipe working fluid, using internal and external measurements to quantify the heat transport in the heat pipe. A 25.4 mm outer diameter, 316 stainless steel tube was used for the heat pipe testing. Ten wraps of 100 × 100 (100 openings per inch) 316 stainless steel screen mesh were used as the wick, with a sliding fit and no annular gap. A fill ratio of 103 % of the total wick void volume was used. An air jacket was attached to the condenser of the heat pipe for cooling. Internal and external temperature measurement was performed, utilizing optical fiber distributed temperature sensing and conventional thermocouples, respectively. All tests conducted were in the horizontal orientation. The test matrix consisted of three different cooling conditions, controlled by changing the flow rate of air in the jacket over the condenser, with multiple power levels for each cooling condition. It was found that the thermal resistance of the heat pipe is not influenced directly by the cooling flow rate but is instead linked to the operating temperature. A minimum thermal resistance of 0.58 °C/W was achieved at the highest operating temperature tested of 274 °C. This corresponds to a maximum effective thermal conductivity of 2300  W/m·K. This finding agrees with values from previous studies. Internal vapor temperature measurements determined the active condenser length, where vapor condenses—a useful tool in heat pipe design. The capillary limit, which governs power transport in heat pipes, was exceeded in all tests without dryout, suggesting Dowtherm A outperformed expectations. This finding questions the soundness of the commonly used theoretical capillary limit, as applied for organic fluids such as Dowtherm A. Collectively, these findings highlight Dowtherm A’s viability for use in medium-temperature heat pipes, offering improved efficiency and operational safety in diverse energy systems.
带内蒸汽监测的Dowtherm A热管性能分析
在200-600°C范围内工作的中温热管广泛应用于核微反应堆,太阳能集热器,热能储存和空间等领域。高效的被动传热装置,如热管,对于在此温度范围内运行的电力系统至关重要。尽管适用范围很广,但在中温条件下,热管的传统工质往往表现不佳,因此需要对这些工质进行更多的研究。Dowtherm A因其与热管材料的化学相容性、低毒性、低可燃性和足够的热水力特性而具有吸引力,而这些特性对于大多数中温热管工作流体来说都是不可能的。本实验研究了Dowtherm A作为中温热管工质的性能,使用内部和外部测量来量化热管中的热量传递。热管试验采用外径25.4 mm的316不锈钢管。使用10层100 × 100(每英寸100个开口)的316不锈钢筛网作为灯芯,具有滑动配合,没有环形间隙。填充率为芯芯总空隙体积的103%。在热管的冷凝器上安装了一个空气夹套用于冷却。利用光纤分布式温度传感和传统热电偶分别进行了内部和外部温度测量。所有测试都是在水平方向进行的。测试矩阵由三种不同的冷却条件组成,通过改变冷凝器上方导管套中的空气流量来控制,每种冷却条件具有多个功率水平。研究发现,热管的热阻不受冷却流量的直接影响,而与工作温度有关。在测试的最高工作温度为274℃时,最小热阻为0.58℃/W。这相当于最大有效导热系数为2300 W/m·K。这一发现与之前的研究结果一致。内部蒸汽温度测量确定了主动冷凝器的长度,其中蒸汽冷凝-热管设计的有用工具。在没有干燥的情况下,所有测试都超过了控制热管中电力传输的毛细管极限,这表明Dowtherm A的表现超出了预期。这一发现质疑了常用的理论毛细管极限的合理性,如应用于有机流体,如Dowtherm A。总的来说,这些发现突出了Dowtherm A在中温热管中使用的可行性,在不同的能源系统中提供了更高的效率和操作安全性。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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