Investigation of heat transfer at supercritical pressures began as early as the 1930s with the study of free-convection heat transfer to fluids at a near-critical point. In the 1950s, the concept of using supercritical “steam” to increase thermal efficiency of fossil-fired thermal power plants became an attractive option. Germany, USA, the former USSR, and some other countries extensively studied supercritical heat transfer during the 1950s till the 1980s. This research was primarily focused on bare circular tubes cooled with SuperCritical Water (SCW). However, some studies were performed with modeling fluids such as SC carbon dioxide and refrigerants instead of SCW. Currently, the use of supercritical “steam” in fossil-fired thermal power plants is the largest industrial application of fluids at supercritical pressures.Near the end of the 1950s and at the beginning of the 1960s, several studies were conducted to investigate a potential of using SCW as a coolant in nuclear reactors. However, these activities were abandoned for some time and regain momentum in 1990s. In support of development of SuperCritical Water-cooled nuclear-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 SC Pressures (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, i.e., grids, end plates, spacers, bearing pads, fins, ribs, etc.). New experiments in 1990s–2000s were triggered by several reasons: 1) thermophysical properties of SCW have been updated from 1950s to 1970s, e.g., a peak in thermal conductivity in the critical/pseudocritical points was “officially” introduced in 1990s; 2) experimental techniques have been improved; 3) in SCWRs various bundle flow geometries will be used instead of bare-tube geometry; and 4) in SC steam generators of thermal power plants larger diameter tubes/pipes (20–40 mm) are used, however, in SCWRs hydraulic-equivalent diameters of proposed bundles will be within 5–12 mm.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 a reliable, accurate and wide-range SCW heat-transfer correlation to be used. Therefore, the objective of this paper is to summarise in concise form the work performed concerning with the heat transfer at SCPs, based mainly on examples of water, carbon dioxide, and R-12.
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