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Featured researches published by Seong-O Kim.


Nuclear Engineering and Technology | 2007

CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600

Dohee Hahn; Yeong-Il Kim; Chan Bock Lee; Seong-O Kim; Jae-Han Lee; Yong-Bum Lee; Byung-Ho Kim; Hae-Yong Jeong

The Korea Atomic Energy Research Institute has developed an advanced fast reactor concept, KALIMER-600, which satisfies the Generation IV reactor design goals of sustainability, economics, safety, and proliferation resistance. The concept enables an efficient utilization of uranium resources and a reduction of the radioactive waste. The core design has been developed with a strong emphasis on proliferation resistance by adopting a single enrichment fuel without blanket assemblies. In addition, a passive residual heat removal system, shortened intermediate heat-transport system piping and seismic isolation have been realized in the reactor system design as enhancements to its safety and economics. The inherent safety characteristics of the KALIMER-600 design have been confirmed by a safety analysis of its bounding events. Research on important thermal-hydraulic phenomena and sensing technologies were performed to support the design study. The integrity of the reactor head against creep fatigue was confirmed using a CFD method, and a model for density-wave instability in a helical-coiled steam generator was developed. Gas entrainment on an agitating pool surface was investigated and an experimental correlation on a critical entrainment condition was obtained. An experimental study on sodium-water reactions was also performed to validate the developed SELPSTA code, which predicts the data accurately. An acoustic leak detection method utilizing a neural network and signal processing units were developed and applied successfully for the detection of a signal up to a noise level of -20 dB. Waveguide sensor visualization technology is being developed to inspect the reactor internals and fuel subassemblies. These research and developmental efforts contribute significantly to enhance the safety, economics, and efficiency of the KALIMER-600 design concept.


Numerical Heat Transfer Part B-fundamentals | 2011

Comparative Analysis of Thermal Models in the Lattice Boltzmann Method for the Simulation of Natural Convection in a Square Cavity

Seok-Ki Choi; Seong-O Kim

In this article, a comparative analysis of thermal models in the lattice Boltzmann method for the simulation of natural convection in a square cavity is presented. A hybrid method, in which the thermal equation is solved by the Navier-Stokes equation method while the mass and momentum equations are solved by the lattice Boltzmann method (LBM), is introduced and its merits are explained. All the governing equations are discretized on a cell-centered, nonuniform grid using the finite-volume method. The convection terms are treated by a second-order central-difference scheme with a deferred-correction method to ensure accuracy of solutions. The resulting algebraic equations are solved by a strongly implicit procedure. The hybrid method is applied to the simulation of natural convection in a square cavity and the predicted results are compared with the benchmark solutions given in the literatures. The predicted results are also compared with those by the double-population LBM and by the Navier-Stokes equation method. In general, the present hybrid method is as accurate as the Navier-Stokes equation method and the double-population LBM. The hybrid method shows better convergence and stability than the double-population LBM. These observations indicate that this hybrid method is an efficient and economic method for the simulation of incompressible fluid flow and heat transfer problems involving complex geometries.


Numerical Heat Transfer Part A-applications | 2014

Computation of the Natural Convection of Nanofluid in a Square Cavity with Homogeneous and Nonhomogeneous Models

Seok-Ki Choi; Seong-O Kim; Tae-Ho Lee; Dohee-Hahn

A numerical study of a laminar natural convection of the CuO-water nanofluid in a square cavity using homogeneous and nonhomogeneous models is presented. All the governing equations including the volume fraction equation are discretized on a cell-centered, nonuniform grid employing the finite-volume method with a primitive variable formulation. Calculations are performed over a range of Rayleigh numbers (Raf = 104–107) and volume fractions of the nanoparticle (0.01 ≤ Φ ≤ 0.1). From the computed results, it is shown that both the homogeneous and nonhomogeneous models predict the deterioration of the natural convection heat transfer well with an increase of the volume fraction of nanoparticle at the same Rayleigh number, which was observed in the previous experimental studies. It is also shown that the differences in the computed results of the average Nusselt number at the wall between the homogeneous and nonhomogeneous models are very small, and this indicates that the slip mechanism of the Brown diffusion and thermophoresis effects are negligible in the laminar natural convection of the nanofluid. The degradation of the heat transfer with an increase of the volume fraction of the nanoparticle in the natural convection of nanofluid is due to the increase of the viscosity and the decrease of the thermal expansion coefficient and the specific heat. It is clarified in the present study that the previous controversies between the numerical and experimental studies are owing to the different definitions of the Nusselt number.


Nuclear Engineering and Technology | 2009

ADVANCED SFR DESIGN CONCEPTS AND R&D ACTIVITIES

Dohee Hahn; Jinwook Chang; Young-In Kim; Yeong-Il Kim; Chan Bock Lee; Seong-O Kim; Jae-Han Lee; Kwi-Seok Ha; Byung-Ho Kim; Yong-Bum Lee

In order to meet the increasing demand for electricity, Korea has to rely on nuclear energy due to its poor natural resources. In order for nuclear energy to be expanded in its utilization, issues with uranium supply and waste management issues have to be addressed. Fast reactor system is one of the most promising options for electricity generation with its efficient utilization of uranium resources and reduction of radioactive waste, thus contributing to sustainable development. The Korea Atomic Energy Research Institute (KAERI) has been performing R&Ds on Sodium-cooled Fast Reactors (SFRs) under the national nuclear R&D program. Based on the experiences gained from the development of KALIMER conceptual designs of a pool-type U-TRU-10%Zr metal fuel loaded reactor, KAERI is currently developing Advanced SFR design concepts that can better meet the Generation IV technology goals. This also includes developing, Advanced SFR technologies necessary for its commercialization and basic key technologies, aiming at the conceptual design of an Advanced SFR by 2011. KAERI is making R&D efforts to develop advanced design concepts including a passive decay heat removal system and a supercritical CO 2 Brayton cycle energy conversion system, as well as developing design methodologies, computational tools, and sodium technology. The long-term Advanced SFR development plan will be carried out toward the construction of an Advanced SFR demonstration plant by 2028.


Nuclear Engineering and Technology | 2009

A SIMPLE ANALYTICAL METHOD FOR NONLINEAR DENSITY WAVE TWO-PHASE INSTABILITY IN A SODIUM-HEATED AND HELICALLY COILED STEAM GENERATOR

Seong-O Kim; Seok-Ki Choi; Han-Ok Kang

A simple model to analyze non-linear density-wave instability in a sodium-cooled helically coiled steam generator is developed. The model is formulated with three regions with moving boundaries. The homogeneous equilibrium flow model is used for the two-phase region and the shell-side energy conservation is also considered for the heat flux variation in each region. The proposed model is applied to the analysis of two-phase instability in a JAEA (Japan Atomic Energy Agency) 50MWt No.2 steam generator. The steady state results show that the proposed model accurately predicts the six cases of operating temperatures on the primary and secondary sides. The sizes of three regions, the secondary side pressure drop according to the flow rate, and the temperature variation in the vertical direction are also predicted well. The temporal variations of the inlet flow rate according to the throttling coefficient, the boiling and superheating boundaries and the pressure drop in the two-phase and superheating regions are obtained from the unsteady analysis.


Nuclear Technology | 2011

SODIUM-CO2 INTERACTION IN A SUPERCRITICAL CO2 POWER CONVERSION SYSTEM COUPLED WITH A SODIUM FAST REACTOR

Jae-Hyuk Eoh; Hee Cheon No; Yong-Hwan Yoo; Seong-O Kim

Abstract For the supercritical CO2 Brayton cycle of a sodium-cooled fast reactor, we carried out surface reaction tests for sodium temperatures ranging from 200 to 600°C. Based on the test results, we found that the reaction kinetics over the sodium temperature range of 300 to 550°C depends heavily on the temperature but is not sensitive to the velocity of CO2 flowing over the gas-liquid reacting interface explored in this study. Gaseous and nongaseous reaction products were sampled and analyzed quantitatively. The rates of the chemical reaction were determined by measuring the gas concentration of the CO/CO2 mixture. Then, we proposed a two-zone reaction model with a threshold temperature of 460°C. The kinetic parameters for each reaction zone were experimentally obtained.


Numerical Heat Transfer Part B-fundamentals | 2012

Computation of Turbulent Natural Convection in a Rectangular Cavity with the Lattice Boltzmann Method

Seok-Ki Choi; Seong-O Kim; Tae-Ho Lee; Yeong-Il Kim; Dohee Hahn

A numerical study of a turbulent natural convection in a rectangular cavity with the lattice Boltzmann method (LBM) is presented. The primary emphasis of the present study is placed on investigation of accuracy and numerical stability of the LBM for the turbulent natural-convection flow. A HYBRID method in which the thermal equation is solved by the conventional Reynolds-averaged Navier-Stokes equation (RANS) method while the conservation of mass and momentum equations are resolved by the LBM is employed in the present study. The elliptic-relaxation model is employed for the turbulence model and the turbulent heat fluxes are treated by the algebraic flux model. All the governing equations are discretized on a cell-centered, nonuniform grid using the finite-volume method. The convection terms are treated by a second-order central-difference scheme with the deferred correction method to ensure accuracy and stability of solutions. The present LBM is applied to the prediction of a turbulent natural convection in a rectangular cavity and the computed results are compared with the experimental data commonly used for the validation of turbulence models and those by the conventional finite-volume method. It is shown that the LBM with the present HYBRID thermal model predicts mean velocity components and turbulent quantities which are as good as those by the conventional finite-volume method. It is also found that the accuracy and stability of the solution is significantly affected by the treatment of the convection term, especially near the wall.


Journal of Nuclear Science and Technology | 2010

Wastage and Self-Plugging by a Potential CO2 Ingress in a Supercritical CO2 Power Conversion System of an SFR

Jae-Hyuk Eoh; Hee Cheon No; Yong-Hwan Yoo; Ji-Young Jeong; Jong-Man Kim; Seong-O Kim

For a CO2 ingress accident into liquid sodium in a supercritical CO2 power conversion system coupled with a sodium-cooled fast reactor, we investigated two major design issues: i) a wastage phenomenon in regard to structural damage adjacent to the leaking position, and ii) potential channel plugging due to the formation of a particulate reaction product. In order to understand the factors affecting the occurrence of these issues, two kinds of experiments were carried out: a wastage effect test and a self-plugging test. All experimental conditions were chosen to reasonably represent the normal operating conditions and realistic design parameters of the reference plant. The test results indicate the absence of wastage, which will not lead to additional tube ruptures and damage propagation. In the current experiment, the self-plugging of PCHE channels only took place under two limited conditions: i) the sodium temperature is over 500°C and ii) the equivalent diameter of the crack opening is less than 1.5mm with a small leakage rate of far less than 1 g/s of CO2 ingress.


Nuclear Engineering and Technology | 2009

DEVELOPMENT OF A SIMPLIFIED MODEL FOR ANALYZING THE PERFORMANCE OF KALIMER-600 COUPLED WITH A SUPERCRITICAL CARBON DIOXIDE BRAYTON ENERGY CONVERSION CYCLE

Seung-Hwan Seong; Tae-Ho Lee; Seong-O Kim

A KALIMER-600 concept which is a type of sodium-cooled fast reactor, has been developed at KAERI. It uses sodium as a primary coolant and is a pool-type reactor to enhance safety. Also, a supercritical carbon dioxide (CO₂) Brayton cycle is considered as an alternative to an energy conversion system to eliminate the sodium water reaction and to improve efficiency. In this study, a simplified model for analyzing the thermodynamic performance of the KALIMER-600 coupled with a supercritical CO₂ Brayton cycle was developed. To develop the analysis model, a commercial modular modeling system (MMS) was adopted as a base engine, which was developed by nHance Technology in USA. It has a convenient graphical user interface and many component modules to model the plant. A new user library for thermodynamic properties of sodium and supercritical CO₂ was developed and attached to the MMS. In addition, some component modules in the MMS were modified to be appropriate for analysis of the KALIMER-600 coupled with the supercritical CO₂ cycle. Then, a simplified performance analysis code was developed by modeling the KALIMER-600 plant with the modified MMS. After evaluating the developed code with each component data and a steady state of the plant, a simple power reduction and recovery event was evaluated. The results showed an achievable capability for a performance analysis code. The developed code will be used to develop the operational strategy and some control logics for the operation of the KALIMER-600 with a supercritical CO₂ Brayton cycle after further studies of analyzing various operational events.


Nuclear Technology | 2010

New Design Options Free from a Potential Sodium Freezing Issue for a Passive DHR System of KALIMER

Jae-Hyuk Eoh; Ji-Woong Han; Tae-Ho Lee; Seong-O Kim

Abstract To enhance the operational reliability of a purely passive decay heat removal system in KALIMER, which is named PDRC, three design options to prevent sodium freezing in an intermediate decay heat removal circuit were proposed, and their feasibilities have been studied for an entire plant operation mode. The potential candidates for the new design options are (a) the partially immersed DHX concept, (b) the cavity air cooling system–coupled PDRC concept, and (c) the advanced PDRC concept with alternative cooling medium. The design features of each concept are quantitatively evaluated in this study. For all the options, more specific design considerations were made to confirm their feasibility to properly materialize their concepts in a practical system design procedure, and the general definitions for a purely passive concept and its design features have been discussed as well.

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Seyun Kim

Electric Power Research Institute

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Byong-Jo Yun

Pusan National University

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Goon-Cherl Park

Seoul National University

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Jae-Han Lee

Korea Electric Power Corporation

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