Kihwan Kim

Dr. Kihwan Kim

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Research Focus & Metrics

Academic Career Length

13Years (2014-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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1 December 2021 in Nuclear Engineering and Technology
Verified
Journal Article
Open access
KKKihwan Kim
Kihwan Kim
JLJae Bong Lee
Jae Bong Lee
WKWoo-Shik Kim
Woo-Shik Kim
HCHae-Seob Choi
Hae-Seob Choi
JKJong-In Kim
Jong-In Kim

23 July 2021 in Energies
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Journal Article
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WKWoo Shik Kim
Woo Shik Kim
JLJae Bong Lee
Jae Bong Lee
KKKihwan Kim
Kihwan Kim
Pressure drop across the moisture separator installed in the steam generator of a nuclear power plant affects the power generation efficiency, and so accurate pressure drop prediction is important in generator design. In this study, an empirical correlation is proposed for predicting the two-phase pressure drop through a moisture separator. To ensure the applicability of the correlation, a series of two-phase air-water experiments were performed, and the results of the present test and of the benchmark test of high-pressure steam-water were used in developing the correlation. Based on the experimental results, quality, dimensionless superficial velocity, density ratio of the working fluid, and the geometrical factor were considered to be important parameters. The two-phase pressure drop multiplier was expressed in terms of these parameters. The empirical correlation was found to predict the experimental results within a reasonable range.

1 January 2014 in Science and Technology of Nuclear Installations
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Journal Article
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KKKihwan Kim
Kihwan Kim
BKByoung Jae Kim
Byoung Jae Kim
YYYoung-Jung Youn
Young-Jung Youn
HCHae-Seob Choi
Hae-Seob Choi
SMSang-Ki Moon
Sang-Ki Moon
CSChul-Hwa Song
Chul-Hwa Song
During the reflood phase of a large-break loss-of-coolant accident (LBLOCA) in a pressurized-water reactor (PWR), the fuel rods can be ballooned or rearranged owing to an increase in the temperature and internal pressure of the fuel rods. In this study, an experimental study was performed to understand the thermal behavior and effect of the ballooned region on the coolability using a 2 × 2 rod bundle test facility. The electrically heated rod bundle was used and the ballooning shape of the rods was simulated by superimposing hollow sleeves, which have a 90% blockage ratio. Forced reflood tests were performed to examine the transient two-phase heat transfer behavior for different reflood rates and rod powers. The droplet behaviors were also investigated by measuring the velocity and size of droplets near the blockage region. The results showed that the heat transfer was enhanced in the downstream of the blockage region, owing to the reduced flow area of the subchannel, intensification of turbulence, and deposition of the droplet.

28 October 2021 in Energies
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Journal Article
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KKKihwan Kim
Kihwan Kim
WKWoo Shik Kim
Woo Shik Kim
JLJae Bong Lee
Jae Bong Lee
The most important design parameters of a moisture separator to optimize the efficiency of a nuclear power plant are the moisture carry over and pressure drop. An air-water test facility was constructed to evaluate the design parameters for various types of conventional moisture separators in Korea. In this study, a half scale of swirl-vane separator was designed, and test conditions were defined based on the scaling law to cover a wide range of operating conditions. The moisture carry over was measured using an isokinetic sampling system for 34 different flow conditions. The MCO was in range of 0.30–7.05% according to the test conditions. Single and two-phase flow experiments were also carried out to identify the two-phase pressure drop characteristics. Based on the obtained results, the proposed empirical correlation model was extended to a submerged separator and applying these results to a full scale system is discussed in this paper.

3 June 2024 in Energies
Verified
Journal Article
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KKKihwan Kim
Kihwan Kim
WKWoo Shik Kim
Woo Shik Kim
HCHae-Seob Choi
Hae-Seob Choi
HSHyosung Seol
Hyosung Seol
BLByung-Jun Lim
Byung-Jun Lim
DEDong-Jin Euh
Dong-Jin Euh
The experimental data of core flow distribution are indispensable for obtaining licensing and facilitating the design of fluid systems of nuclear reactors. In this study, an Advanced power reactor Core flow and Pressure (ACOP) test facility was established to experimentally simulate the internal flow of the Advanced Power Reactor 1000 (APR1000) on a reduced length scale of 1/5. The core region was simulated by using 177 core simulators representing the fuel assemblies of the APR1000. The APR1000 flow distributions were synthetically identified by accurately measured parameters: the core inlet flow rate and outlet pressure under the four-pump balanced and unbalanced flow conditions. The overall inlet flow rates ranged from 87.7% to 112.0% relative to the averaged flow rate. Here, we scrutinize the flow distributions considering the flow conditions and internal structures and briefly describe the applied scaling method and design concept of the test facility.

24 July 2021 in Science and Technology of Nuclear Installations
Verified
Journal Article
Open access
PDF file
KKKihwan Kim
Kihwan Kim
WKWoo Shik Kim
Woo Shik Kim
JLJae Bong Lee
Jae Bong Lee
WJWoo-Jin Jeon
Woo-Jin Jeon
The moisture carryover (MCO) of the primary separator in a steam generator is the most important design parameter to ensure high efficiency in a steam generator. There is an inherent limitation to experimentally evaluate the MCO under the prototype conditions. In this study, the air/water test facility was constructed based on the similarity law, and a new isokinetic system was developed to quantify the MCO. Several experiments were performed for the mass quality ranging from 0.315 to 0.382. The accuracy and versatility of the experimental method was verified experimentally using a full and half scale of separators. The test results were compared with the prototype results. It was proved to be a reliable experimental method for evaluating the MCO of the moisture separator.