TK
Tae-Soon Kwon

Well Cited

64
Works
449
Citations
11
H-Index
Search Authors
Author Statistics
  • OpenAlex ID A5112978516
  • i10-Index 13
  • 2-Yr Mean Citedness 0.00
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Tae-Soon Kwon

Also known as: T. S. Kwon, T.S Kwon, T.S. Kwon, Tae Soon Kwon, Tae-Soon Kwon

64

Total Works

449

Citations

11

H-Index

13

i10-Index

Citation & Works Trend by Year
26 years active
Top Research Topics
Nuclear Engineering Thermal-Hydraulics (58) Nuclear reactor physics and engineering (41) Heat transfer and supercritical fluids (24) Nuclear and radioactivity studies (20) Heat Transfer and Boiling Studies (14)
Recent Publications
15 shown
Year Publication Title Citations Action
2025 Establishing and Assessing of a Leak Collection System Analysis Method by Computational Fluid Dynamics Modelling and Simulation in Engineering 0
2024 Development of 16N monitoring system for real-time detection of small leakage in reactor coolant systems Progress in Nuclear Energy 5
2023 Development of a RCS Coolant Leak Detection System for Reactor Safety Enhancement The KSFM Journal of Fluid Machinery 1
2023 Establishment and Evaluation of Leak Collection System Analysis Method Using CFD Analysis The KSFM Journal of Fluid Machinery 0
2023 Performance Verification of Reactor Unidentified Leakage Detection System The KSFM Journal of Fluid Machinery 1
2023 Steam-Jet Evaluation for Predicting Leakage Behavior and Interpretation of Experimental Verification Science and Technology of Nuclear Installations 1
2021 Development of a Unidentified RCS Leakage Detection Sensor System Less than 0.5 gpm The KSFM Journal of Fluid Machinery 4
2021 A review of meta-stable aspects on a subcooled critical flow in nozzles and orifices Annals of Nuclear Energy 6
2021 Investigation of Characteristics on Subcooled Critical Flowrate in Orifices The KSFM Journal of Fluid Machinery 1
2020 원전 내 배관의 증기 누설 사고 시 누설 탐지 포집/이송 시스템 예비 해석 0
2020 Preliminary Analysis of a Sampling and Transportation System for Leak Detection during Steam Leak Accident of a Pipe in Nuclear Power Plants Transactions of the Korean Society of Pressure Vessels and Piping 1
2019 Investigation of Leakage Characteristics on Major Equipment/Component in Reactor System The KSFM Journal of Fluid Machinery 4
2019 BORON MIXING IN A REACTOR CORE AND DOWNCOMER Proceeding of Second Thermal and Fluids Engineering Conference 0
2017 Contribution of thermal–hydraulic validation tests to the standard design approval of SMART Nuclear Engineering and Technology 23
2017 HEAT TRANSFER AND PRESSURE DROP CHARACTERISTICS OF AIR COOLED FINNED TUBE HEAT EXCHANGER Proceeding of Second Thermal and Fluids Engineering Conference 0

Data source: OpenAlex API