Heat Transfer in Supercritical Fluids: A Review

Author(s):  
Kapil Bodkha ◽  
N.K. Maheshwari

Abstract SuperCritical (SC) fluids find potential applications in the upcoming energy systems due to various advantages associated with them. One of such applications is nuclear reactor where supercritical water and carbon-dioxide, both are proposed as the coolants in advanced reactor designs. Higher efficiency, simplified systems, lower operational costs are some of the advantages which propels the research fraternity to employ these fluids in application. However, there are also some challenges associated with the use of these fluids. Heat transfer behaviour of these fluids is one among them. As SC fluids undergo tremendous changes in thermo-physical properties across pseudo-critical point, heat transfer may get affected. It may get enhanced, deteriorated or remain unaltered. Various studies, experimental and analytical, have been carried out in the past using SC fluids to evaluate their heat transfer behavior. Various heat transfer correlations have been proposed by researchers catering to different operating range of parameters. Also, studies have been dedicated by researchers to investigate fluid-to-fluid scaling of SC fluids based on which scaling laws were proposed by them. This way prototypic fluid behavior can be predicted if the model fluid conditions are known. This paper presents a latest review of the scaling laws and heat transfer correlations applicable to SC fluids. Illustrations have also been presented considering reference experimental data from literature to get a feel about how these scaling laws fare among themselves. Various heat transfer correlations have been compared and important observations have also been discussed in this article.

Author(s):  
Hakim Maloufi ◽  
Hanqing Xie ◽  
Andrew Zopf ◽  
William Anderson ◽  
Christian Langevin ◽  
...  

Currently, there is a number of Generation-IV SuperCritical Water-cooled nuclear-Reactor (SCWR) concepts under development worldwide. These high temperature and pressure reactors will have significantly higher operating parameters compared to those of current water-cooled nuclear-power reactors (i.e., “steam” pressures of about 25 MPa and “steam” outlet temperatures up to 625 °C). Additionally, SCWRs will have a simplified flow circuit in which steam generators, steam dryers, steam separators, etc. will be eliminated, as the steam will be flowing directly to a steam turbine. In support of developing SCWRs studies are being conducted on heat transfer at SuperCritical Pressures (SCPs). Currently, there are very few experimental datasets for heat transfer at SCPs in power-reactor fuel bundles to a coolant (water) available in open literature. Therefore, for preliminary calculations, heat-transfer correlations developed with bare-tube data can be used as a conservative approach. Selected empirical heat-transfer correlations, based on experimentally obtained datasets, have been put forward to calculate Heat Transfer Coefficients (HTCs) in forced convective in various fluids, including water at SCPs. The Mokry et al. correlation (2011) has shown a good fit for experimental data at supercritical conditions within a wide range of operating conditions in Normal and Improved Heat-Transfer (NHT and IHT) regimes. However, it is known that a Deteriorated Heat-Transfer (DHT) regime appears in bare tubes earlier than that in bundle flow geometries. Therefore, it is important to know if bare-tube heat-transfer correlations for SCW can predict HTCs at heat fluxes beyond those defined as starting of DHT regime in bare tubes. The Mokry et al. (2011) correlation fits the best SCW experimental data for HTCs and inner wall temperature for bare tubes at SCPs within the NHT and IHT regimes. However, this correlation might have problems with convergence of iterations at heat fluxes above 1000 kW/m2.


Author(s):  
Weiqiang Zhang ◽  
Huixiong Li ◽  
Qing Zhang ◽  
Yifang Zhang ◽  
Tai Wang

The investigation on the heat transfer characteristics for supercritical pressure water (SCW) is of value for the development of the supercritical water-cooled nuclear reactor (SCWR). As an important heat transfer enhancement element, heat transfer for SCW in internally-ribbed tubes was still not solved, though lots of experimental studies have been published and a great many heat transfer correlations were proposed. This paper presented an analysis of heat transfer in the internally-ribbed tubes, through comparing heat transfer correlations for SCW gained from different internally-ribbed tubes under the same operating condition. It was found that all existing heat transfer correlations reported could not been well applied for various internally-ribbed tubes with large deviation between prediction results and experimental values, because rib geometry had a great influence on heat transfer of internally-ribbed tubes. On the basis of experimental data collected from open literature for internally-ribbed tubes, a new general calculation correlation of heat transfer coefficient for SCW was developed for various internally-ribbed tubes by combining an optimized empirical correlation for vertically-upward smooth tubes and four dimensionless numbers of rib geometry. The results show that the calculated values of the new present correlation is in reasonable agreement with available experimental data collected. Moreover, the new correlation was verified well by experiment data of two new-type internally-ribbed tubes performed beyond the above experimental database.


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