An overview of measurements, data compilations and prediction methods for the critical heat flux in water-cooled tubes

Groeneveld, D.C.; Ireland, A.; Kaizer, Joshua; Vasić, A.Ž

doi:10.1016/j.nucengdes.2018.02.031

Cited by 18 publications

(4 citation statements)

References 34 publications

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“…Typically, the temperature regime of the evaporator pipe wall is determined using internal cooling conditions mentioned by Groeneveld et al, [13]. The high intensity of heat transfer during boiling can be ensured by continuously wetting the inner surface of the wall with liquid.…”

Section: Literature Reviewmentioning

confidence: 99%

Advanced Natural Circulation Model in Evaporation Circuits of Thermosiphon Waste Heat Boilers

Dolganov Iurii,

Epifanov Alexander,

Lychko Bohdan

2024

ARFMTS

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Although existing models of natural circulation in steam boilers involve numerous simplifications, the physical processes that occur in real-time are not considered. This study sought to improve the natural circulation model in the evaporation circuit of a thermosiphon waste heat boiler using an analytical solution and numerical simulation results. A modified natural circulation model was developed using ranked variables of velocity and heat flux in the evaporator ring channels. These results were obtained in the range of heat flux densities 1.074–9.973 kW/m2 and temperatures of the thermosiphons hot zone 477.4–487.1 K which is typical for a waste heat boiler for cogeneration power plant with gas turbine engine 6700 kW power.

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Section: Literature Reviewmentioning

confidence: 99%

Advanced Natural Circulation Model in Evaporation Circuits of Thermosiphon Waste Heat Boilers

Dolganov Iurii,

Epifanov Alexander,

Lychko Bohdan

2024

ARFMTS

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“…In the nuclear industry, a tremendous effort has been invested regarding two-phase flow phenomena especially for the critical heat flux (CHF) condition [14][15][16]. The nucleate boiling (low heat flux regime) enhances the heat transfer rate by inducing vigorous convection phenomenon aided by phase change.…”

Section: Introductionmentioning

confidence: 99%

Mechanism of critical current density in water electrolysis utilizing analogous relation with critical heat flux at boiling system

Park

2024

Preprint

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The boiling and hydrogen evolving systems both exhibit an N-shaped curve, which includes the peak point representing the critical heat flux (CHF) in boiling system and the critical current density (CCD) in hydrogen evolving system. Since the CCD can be regarded as a maximum manageable current density, it would be an obstacle limiting the hydrogen generation rate in a water electrolysis. However, none of previous work proposed a mechanism leading to the CCD and tried to establish a correlation so far. In the nuclear industry, tremendous efforts have been invested to develop the CHF model so that the correlations were developed, which predict the CHF well. Based on the analogous relation between the two systems, the present study explores compatibility of the CHF correlation to the CCD phenomenon. The critical superficial velocity converted from the CHF correlation was compared with that from the measured CCD. The result shows that the critical superficial velocity from the experiment was about 100 times smaller than that from the CHF correlation due to the remarkably higher active nucleation site density of the hydrogen evolving system. In a phenomenological perspective, the critical number of bubbles, which hinders the heat or mass transfer was estimated within similar value between the two systems. It is concluded that the CCD phenomenon is governed by the hydrodynamic behavior of the bubbles adjacent to the cathode surface, which depends strongly on the active nucleation site density, while the CHF can be predicted only by the physical properties of the fluid.

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“…For example, the pressure ranges from 2 to 17 MPa, the mass flux ranges from several hundred to nearly 5,000 kg/m 2 s, and the corresponding equilibrium quality ranges from −0.2 to 0.5. Obviously, such a wide range of thermalhydraulic parameters may cover different CHF regimes (Groeneveld et al, 2018).…”

Section: Introductionmentioning

confidence: 99%

Investigation on Rod Bundle CHF Mechanistic Model for DNB and DO Prediction Under Wide Parameter Range

et al. 2021

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For a water cooled reactor, the key thermal-hydraulic parameters span a wide range corresponding to different CHF regimes. Under accident conditions, due to the flow regime transition and interchannel mixing effect, the corresponding CHF can transition from the DO to DNB regime. In order to continuously and accurately predict DNB and DO regime CHF under wide parameter range for rod bundle channel, a comprehensive CHF mechanistic model covering the DNB and DO regime CHF prediction is established based on the rod bundle CHF-regime criterion. The DNB regime CHF mechanistic model of superheated liquid layer depletion under turbulence fluctuation bubbles and the mature DO regime CHF mechanistic model are combined to form the comprehensive CHF model. Furthermore, the comprehensive CHF model is assessed by 5 × 5 rod bundle CHF experimental data independently obtained by the Nuclear Power Institute of China (NPIC). The statistical evaluation and parametric trend analysis show that the maximum mean error of P/M is within ±22%, and the local pressure, mass flux, and quality do not have any effects on the average deviations of the predicted flux P from the measured flux M. This indicates that the comprehensive CHF mechanistic model can accurately and continuously predict the DNB and DO regime CHF in the rod bundle channel.

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An overview of measurements, data compilations and prediction methods for the critical heat flux in water-cooled tubes

Cited by 18 publications

References 34 publications

Advanced Natural Circulation Model in Evaporation Circuits of Thermosiphon Waste Heat Boilers

Advanced Natural Circulation Model in Evaporation Circuits of Thermosiphon Waste Heat Boilers

Mechanism of critical current density in water electrolysis utilizing analogous relation with critical heat flux at boiling system

Investigation on Rod Bundle CHF Mechanistic Model for DNB and DO Prediction Under Wide Parameter Range

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