Thermal-Hydraulic Tests and Analyses for the Apr1400's Development and Licensing

Song, Chul-Hwa; Baek, Won-Pil; Park, Jong-Kyun

doi:10.5516/net.2007.39.4.299

Cited by 31 publications

(11 citation statements)

References 5 publications

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“…In addition, the safety analysis for the APR1400 (Korean advanced power reactor) showed that subcooled boiling phenomena in the reactor downcomer results in a reduction of the reflood flow rate for the core cooling during a postulated large break loss of coolant accident (LBLOCA). (Yun, 2006, Song, 2007 For a better prediction of these subcooled boiling phenomena, development of advanced analysis tools or an improvement of the related models for the existing prediction tools is still required. For this, experimental work for the subcooled boiling phenomena is indispensable.…”

Section: Introductionmentioning

confidence: 99%

Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Yun

Bae

Euh

et al. 2010

Nuclear Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Yun

Bae

Euh

et al. 2010

Nuclear Engineering and Design

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“…1) For the analysis of the two-phase flow, the two-fluid model is considered as a state-of-the-art model that deals with the mass, momentum and energy of each phase. 2) As given in the formulation of the two-fluid model, the interaction between two phases such as the interfacial momentum or heat transfer plays an important role in the dynamics of each phase and is proportional to the interfacial area.…”

Section: Introductionmentioning

confidence: 99%

Computational Analysis of a Subcooled Boiling Flow with a One-group Interfacial Area Transport Equation

Bae

Yoon

Euh

et al. 2008

J. Nucl. Sci. Technol.

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For a multidimensional analysis of a two-phase flow, a computational fluid dynamics (CFD) code was developed with the implementation of an interfacial area transport equation that is beneficial for dynamically estimating the interfacial area concentration (IAC). The code structure was based on the two-fluid model and the Simplified Marker and Cell (SMAC) algorithm. The SMAC algorithm was extended to a two-phase flow simulation with a phase change. Various well-known constitutive models regarding boiling, condensation, and nondrag forces have been implemented into the code. To verify the robustness of the code to predict wall boiling and void propagation phenomena, a subcooled boiling test in a vertical annulus channel was analyzed as a benchmark problem. As the analysis results, a model for bubble departure diameter on the heated wall was identified as the principal factor for subcooled boiling phenomena, and the limitation of the current departure diameter models under a low-pressure condition resulted in a deviation of the void fraction and IAC when compared with the results of the experiment. It is necessary that the research on the interfacial area transport equation focuses on modeling reliable source terms for the boiling mechanism as a future work.

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“…Understanding the hydrodynamics of multidimensional phenomena in two-phase flows is an issue of particular interest in advanced energy conversion systems and modern industrial processes, especially in the development of advanced nuclear reactor systems and their safety analysis [1]. The application of computational fluid dynamics (CFD) codes to two-phase flow allows for safety investigations to obtain some access to smaller-scale flow processes that are not seen by system codes.…”

Section: Introductionmentioning

confidence: 99%

The dependence of wall lubrication force on liquid velocity in turbulent bubbly two-phase flows

Nguyen

Song

Bae

et al. 2013

Journal of Nuclear Science and Technology

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Based on the significance of a computational fluid dynamics (CFD) simulation of dispersed two-phase flow systems in many engineering fields, especially in nuclear energy systems, extensive analytical and numerical studies of wall lubrication force for vertical upward turbulent bubbly two-phase flow are presented. An analytical expression of the wall lubrication force considering the effect of liquid velocity is developed and analyzed. A numerical methodology for evaluating the wall lubrication force coefficients is proposed, which is based on the assumption that the balance of the forces acting on a bubble perpendicularly to the flow direction determines the establishment of radial void fraction profiles. Wall lubrication force coefficients are determined based on a reasonable agreement in radial void fraction profiles between numerical results predicted by the CFD EAGLE (elaborated analysis of gas-liquid flows evolution) code and extensive experimental database in the open literature as well as experiments performed at the Korea Atomic Energy Research Institute-vertical air-water loop test facility. Liquid velocity dependence of wall lubrication force is clearly shown in both analytical and numerical ways in the present study, and new correlations are then proposed for the wall lubrication force coefficients.

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Thermal-Hydraulic Tests and Analyses for the Apr1400's Development and Licensing

Cited by 31 publications

References 5 publications

Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Computational Analysis of a Subcooled Boiling Flow with a One-group Interfacial Area Transport Equation

The dependence of wall lubrication force on liquid velocity in turbulent bubbly two-phase flows

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