Supercritical-Fluids Thermophysical Properties and Heat Transfer in Power-Engineering Applications

I. Pioro
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引用次数: 6

Abstract

Researches on specifics of thermophysical properties and heat transfer at supercritical pressures (SCPs) started as early as the 1930s with the study on free-convection heat transfer to fluids at a near-critical point. In the 1950s, the concept of using SC “ steam ” to increase thermal efficiency of coal-fired thermal power plants became an attractive option. Germany, USA, the former USSR, and some other countries extensively studied heat transfer to SC fluids (SCFs) during the 1950s till the 1980s. This research was primarily focused on bare circular tubes cooled with SC water (SCW). However, some studies were performed with modeling fluids such as SC carbon dioxide and refrigerants instead of SCW. Currently, the use of SC “ steam ” in coal-fired thermal power plants is the largest industrial application of fluids at SCPs. Near the end of the 1950s and at the beginning of the 1960s, several studies were conducted to investigate a possibility of using SCW as a coolant in nuclear reactors with the objective to increase thermal efficiency of nuclear power plants (NPPs) equipped with water-cooled reactors. However, these research activities were abandoned for some time and regained momentum in the 1990s. In support of the development of SCW-cooled nuclear-power reactor (SCWR) concepts, first experiments have been started in annular and various bundle flow geometries. At the same time, more numerical and CFD studies have been performed in support of our limited knowledge on specifics of heat transfer at SCPs in various flow geometries. As the first step in this process, heat transfer to SCW in vertical bare tubes can be investigated as a conservative approach (in general, heat transfer in fuel bundles will be enhanced with various types of appendages, that is, grids, end plates, spacers, bearing pads, fins, ribs, etc.). 1990 by (1) and Rankine cycles with SC carbon dioxide as a working fluid are being developed, etc. A comparison of thermophysical properties of SCFs with those of subcritical-pressure fluids showed that SCFs as single-phase fluids have unique properties, which are close to “ liquid-like ” behavior below critical or pseudocritical points and are quite similar to the behavior of “ gas-like ” substances above these points. A comparison of selected SCW heat transfer correlations has shown that their results may differ from one to another by more than 200%. Based on these comparisons, it became evident that there is a need for reliable, accurate, and wide-range SCW heat transfer correlation(s) to be developed and verified. Therefore, the objective of this chapter is to summarize in concise form specifics of supercritical-fluids thermophysical properties and heat transfer in power-engineering applications.
超临界流体的热物理性质和传热在动力工程中的应用
早在20世纪30年代,人们就开始研究超临界压力下的热物理性质和传热特性,研究流体在近临界点处的自由对流传热。在20世纪50年代,使用SC“蒸汽”来提高燃煤火力发电厂的热效率的概念成为一种有吸引力的选择。从20世纪50年代到80年代,德国、美国、前苏联和其他一些国家广泛研究了超临界流体的传热问题。本研究主要集中在裸圆管用SC水(SCW)冷却。然而,一些研究是用SC、二氧化碳和制冷剂等模拟流体代替SCW进行的。目前,在燃煤热电厂中使用SC“蒸汽”是SCPs中流体的最大工业应用。在20世纪50年代末和60年代初,进行了几项研究,以调查在核反应堆中使用SCW作为冷却剂的可能性,目的是提高配备水冷反应堆的核电站(NPPs)的热效率。然而,这些研究活动被放弃了一段时间,并在20世纪90年代恢复了势头。为了支持SCWR冷却核动力反应堆(SCWR)概念的发展,已经在环空和各种束流几何形状中开始了第一次实验。与此同时,更多的数值和CFD研究已经进行,以支持我们对各种流动几何形状下scp传热细节的有限知识。作为这一过程的第一步,垂直裸管对超临界水的传热可以作为一种保守的方法来研究(一般来说,燃料束中的传热将通过各种类型的附属物来增强,即网格、端板、垫片、轴承座、鳍片、肋等)。正在开发以SC二氧化碳为工作流体的1990 by(1)和Rankine循环等。超临界流体与亚临界压力流体的热物理性质比较表明,超临界流体作为单相流体具有独特的性质,在临界或准临界点以下接近“类液体”行为,而在这些点以上与“类气体”物质的行为非常相似。对所选的SCW传热相关性的比较表明,它们的结果可能彼此差异超过200%。基于这些比较,很明显,需要开发和验证可靠、准确和大范围的SCW传热相关性。因此,本章的目的是以简明的形式总结超临界流体的热物理性质和传热在动力工程应用中的具体情况。
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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