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PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON NUMERICAL ANALYSIS AND APPLIED MATHEMATICS 2014 (ICNAAM-2014) | 2015

Numerical studies on the performance of a flow distributor in tank

Soo Jai Shin; Young In Kim; Seungyeob Ryu; Youngmin Bae; Keung Koo Kim

Flow distributors are generally observed in several nuclear power plants. During core make-up tank (CMT) injection into the reactor, the condensation and thermal stratification are observed in the CMT, and rapid condensation disturbs the injection operation. To reduce the condensation phenomena in the tank, CMT was equipped with a flow distributor. The optimal design of the flow distributor is very important to ensure the structural integrity the CMT and its safe operation during certain transient or accident conditions. In the present study, we numerically investigated the performance of a flow distributor in tank with different shape factors such as the total number of holes, pitch-to-hole diameter ratios, diameter of the hole, and the area ratios. These data will contribute to a design of the flow distributor.


Journal of Energy Engineering-asce | 2015

Development of a thermal-hydraulic analysis code for once-through steam generators using straight tubes for SMRs

Young-Jae Park; Iljin Kim; Kyungjun Kang; Han-Ok Kang; Young In Kim; Hyungdae Kim

A thermal-hydraulic design and performance analysis computer code for a once-through steam generator using straight tubes is developed. To benchmark the developed physical models and computer code, an once-through steam generator developed by other designer is simulated and the calculated results are compared with the design data. Also, the same steam generator is analyzed with the best-estimate thermal-hydraulic system code, MARS, for the code-to-code validation. The overall characteristics of heat transfer area, pressure and temperature distributions calculated by the developed code show general agreements with the published design data as well as the analysis results of MARS. It is demonstrated that the developed code can be utilized for diverse purposes, such as, sensitivity analyses and optimum thermal design of a once-through steam generator.


Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition | 2008

A Study on the Convective Mass Transfer of Nitrogen to Water for a Gas Pressurizing System

Kyoungwoo Seo; Young In Kim; Jae-Kwang Seo; Doo-Jeong Lee

Mass transfer due to a concentration difference of nitrogen can occur in a nuclear system. Our research work seeks to analyze and understand the mass transfer phenomena of nitrogen in water under the condition of a natural convection using the commercially available CFD computer model, FLUENT 6.3. The maximum solubility was employed to express the boundary condition at an interface between the nitrogen and water. First, the case that nitrogen was transferred to water by only a diffusion was simulated to verify the application of the UDS (User defined scalar) model in FLUENT 6.3 for a mass transfer. Diffusion equation, which was described as a PDE (Partial Differential Equation) with non-homogeneous boundary conditions, was solved and the solved results of the PDE showed a good agreement with those of the FLUENT simulation in the same condition. The same cylinder geometry with that of the diffusion case was used to estimate the convective mass transfer. By the natural convection caused by the thermal boundary condition, the mass transfer of nitrogen had a convection effect. The result of FLUENT 6.3 to compute the convective mass transfer showed that the nitrogen was transferred simultaneously in the entire region by the convection effect and it took about several hours until the mole fraction of nitrogen in the water side reached 50% of the maximum saturated value. The averaged mass transfer coefficient was calculated and compared with the results obtained from the heat and mass transfer analogy. The calculated coefficients showed the lower value than those obtained from the various correlations. When the steam mass transfer toward the gas side was negligible, the pressure drop of the gas side due to the reduced nitrogen caused by a mass transfer was computed using the ideal gas law and the Custom Field Function model in the FLUENT 6.3.Copyright


Nuclear Engineering and Design | 2013

CFD analysis of flow distribution at the core inlet of SMART

Youngmin Bae; Young In Kim; Cheon Tae Park


Nuclear Engineering and Design | 2011

Numerical investigation on the similarity of developing laminar flows in helical pipes

Young In Kim; Seong Hoon Kim; Young Dong Hwang; Jong Ho Park


Archive | 2013

Passive safety system of integral reactor

Joo Hyung Moon; Won Jae Lee; Keung Koo Kim; Cheon Tae Park; Young In Kim; Sung Kyun Zee; Keun Bae Park


Archive | 2014

COOLING SYSTEM OF EMERGENCY COOLING TANK AND NUCLEAR POWER PLANT HAVING THE SAME

Young In Kim; Keung Koo Kim; Young Min Bae; Ju Hyeon Yoon; Jae Joo Ha; Won Jae Lee; Tae Wan Kim


Archive | 2013

HEAT EXCHANGER FOR PASSIVE RESIDUAL HEAT REMOVAL SYSTEM

Young Min Bae; Young In Kim; Keung Koo Kim; Seung Yeop Yoo


Archive | 2014

MULTI STAGE SAFETY INJECTION DEVICE AND PASSIVE SAFETY INJECTION SYSTEM HAVING THE SAME

Young In Kim; Keung Koo Kim; Cheon Tae Park; Seung Yeop Yoo; Young Min Bae; Joo Hyung Moon; Soo Jai Shin; Han Ok Kang; Jun Lee; Won Jae Lee; Tae Wan Kim; Keun Bae Park; Ju Hyeon Yoon


Nuclear Engineering and Design | 2014

Safety evaluation of small-break LOCA with various locations and sizes for SMART adopting fully passive safety system using MARS code

Ji-Han Chun; Bub-Dong Chung; Guy-Hyung Lee; Kyoo-Hwan Bae; Young In Kim; Young-Jong Chung; Keung-Koo Kim

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Jun Lee

Ewha Womans University

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Young Soo Kim

Korea Institute of Science and Technology

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