Supercritical water heat transfer for nuclear reactor applications: A review

Rahman, Mohammad Mizanur; Ji, Dongxu; Beni, Mehrdad Shahmohammadi; Hei, Ho Choi; He, Weidong; Zhao, Jiyun

doi:10.1016/j.anucene.2016.06.022

Cited by 66 publications

(8 citation statements)

References 32 publications

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“…Most of the experimental and numerical investigations have been conducted to explore supercritical water and carbon dioxide (sCO 2 ) [12][13][14][15][16][17][18]. Dang and Hihara [19,20] investigated the effects of tube diameter on heat transfer coefficient of sCO 2 under cooling conditions and proposed the modified Gnielinski equation.…”

Section: Introductionmentioning

confidence: 99%

Thermophysical Properties and Supercritical Heat Transfer Characteristics of R515A

Ibrahim¹,

Hu²,

Jiang³

et al. 2021

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The heat transfer of supercritical fluids is a vastly growing field, specifically to find suitable alternative to replace conventional R134a, which can be beneficial for climate change. A considerable suggestion is R515A which possesses considerably lower global warming potential. The present simulations are designed to study supercritical fluid R515A under cooling conditions in horizontal position. The effect of pressure, mass flux, heat flux and tube diameter were considered for horizontal tube in the vicinity of pseudo critical temperature. Numerical investigations on heat transfer characteristics of supercritical fluid R515A were performed using widely used shear-stress transport (SST) model. Moreover, heat transfer correlations were developed and suggested to accurately predict Nusselt number within 10% accuracy. The simulation results showed about 3.98% average absolute deviation.

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Section: Introductionmentioning

confidence: 99%

Thermophysical Properties and Supercritical Heat Transfer Characteristics of R515A

Ibrahim¹,

Hu²,

Jiang³

et al. 2021

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“…A number of investigations have been devoted to the supercritical heat transfer for various fluids [14][15][16][17]. However, while most of these studies were aimed at supercritical water and CO 2 [18][19][20][21], few studies have been devoted to the heat transfer of supercritical kerosene. Edwards [6] and Powell et al [22] carried out a series of experiments on the heat transfer and thermal stability of aviation kerosene for hypersonic propulsion.…”

Section: Introductionmentioning

confidence: 99%

Experiments on Heat Transfer of Supercritical Pressure Kerosene in Mini Tube under Ultra-High Heat Fluxes

et al. 2020

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Heat transfer of supercritical-pressure kerosene is crucial for regenerative cooling systems in rocket engines. In this study, experiments were devoted to measure the heat transfer of supercritical-pressure kerosene under ultra-high heat fluxes. The kerosene flowed horizontally in a mini circular tube with a 1.0 mm inner diameter and was heated uniformly under pressures of 10–25 MPa, mass fluxes of 8600–51,600 kg/m2 s, and a maximum heat flux of up to 33.6 MW/m2. The effects of the operating parameters on the heat transfer of supercritical-pressure kerosene were discussed. It was observed that the heat transfer coefficient of kerosene increases at a higher mass flux and inlet bulk temperature, but is little affected by pressure. The heat transfer of supercritical-pressure kerosene is classified into two regions: normal heat transfer and enhanced heat transfer. When the wall temperature exceeds a certain value, heat transfer is enhanced, which could be attributed to pseudo boiling. This phenomenon is more likely to occur under higher heat flux and lower mass flux conditions. In addition, the experimental data were compared with several existing heat transfer correlations, in which one of these correlations can relatively well predict the heat transfer of supercritical-pressure kerosene. The results drawn from this study could be beneficial to the regenerative cooling technology for rocket engines.

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“…Because of the several related research works on the supercritical fluids (SCFs) conducted in the recent past [1][2][3][4][5][6][7][8][9][10][11][12][13][14] in addition to the decades together related research experience [15][16][17][18][19][20] and based on those findings, it is reasonable to believe that the development of a SCWR is one of the viable options to implement the generation IV nuclear reactor in practice and make it operational in the near future, provided the remaining uncertainties associated with a new possible technology are addressed adequately. The TH stability and the related safety of the SCWR are one of the important identified areas which have received a considerable importance among the concerned scientific community.…”

Section: Introductionmentioning

confidence: 99%

Numerical analysis of parallel-channel density wave instabilities in a supercritical water reactor

Upadhyay

Raghuvanshi

Dutta

2020

J Braz. Soc. Mech. Sci. Eng.

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Supercritical water reactor (SCWR), a possible generation IV nuclear reactor, is expected to be more efficient and economical than the existing reactors. However, the possibility of thermal-hydraulic (TH) instabilities poses a challenge to its development. A generic pressure vessel (PV) SCWR concept, similar to the US SCWR design, is investigated at present for density wave oscillations (DWOs). An existing TH model, which was used earlier for the single-channel analysis, is extended here for the analysis of parallel channels. The TH model accounts for the regional heterogeneity in power distribution. The TH model is validated with the existing numerical results to access its capability to simulate the parallel-channel density wave instabilities (DWIs) in a supercritical water (SCW) system. Then, the TH model is used to capture the core-wide as well as regional modes of parallel-channel DWIs in the PV SCWR. The marginal stability thresholds are obtained for both the modes of DWOs and are compared. Subsequently, the aforementioned stability thresholds are compared with those obtained from the single-channel model as well, with the purpose to quantify the difference in stability thresholds obtained from the single-and parallel-channel analysis.

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Supercritical water heat transfer for nuclear reactor applications: A review

Cited by 66 publications

References 32 publications

Thermophysical Properties and Supercritical Heat Transfer Characteristics of R515A

Thermophysical Properties and Supercritical Heat Transfer Characteristics of R515A

Experiments on Heat Transfer of Supercritical Pressure Kerosene in Mini Tube under Ultra-High Heat Fluxes

Numerical analysis of parallel-channel density wave instabilities in a supercritical water reactor

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