| Advanced thermal fluid leakage detection system with machine learning algorithm for pipe-in-pipe structure H Kim, J Lee, T Kim, SJ Park, H Kim Case Studies in Thermal Engineering 42, 102747, 2023 | 21 | 2023 |
| Design evaluation of large-scale sodium integral effect test facility (STELLA-2) using MARS-LMR J Lee, J Eoh, H Kim, J Yoon, YB Lee, EK Kim, JH Jeong, KL Lee, ... Annals of Nuclear Energy 120, 845-856, 2018 | 14 | 2018 |
| Design and thermal-hydraulic evaluation of the finned-tube type sodium-to-air heat exchanger in sodium test facility H Kim, J Yoon, HY Lee, J Eoh, JY Jeong, J Lee Nuclear Engineering and Design 366, 110755, 2020 | 12 | 2020 |
| Design of electric core simulator system (ECSS) for large-scale integral effect test facility J Lee, J Eoh, JY Jeong, SJ Hong, YH Kim Annals of Nuclear Energy 133, 762-776, 2019 | 10 | 2019 |
| Experimental study on the heat transfer enhancement in sub-channels of 6× 6 rod bundle with large scale vortex flow mixing vanes SJ Byun, CH Shin, J Yoon, H Kim, J Lee, J Eoh, JY Jeong Nuclear Engineering and Design 339, 105-115, 2018 | 10 | 2018 |
| Comparative cost analysis of direct disposal versus pyro-processing with DUPIC in Korea J Lee, JI Lee, WJ Chang, SH Chang Annals of Nuclear Energy 37 (12), 1699-1704, 2010 | 10 | 2010 |
| Experimental study of sodium heat exchanger performance at high Pe number condition using STELLA-1 facility J Lee, H Kim, J Eoh, Y Jung, JW Han, JY Jeong Nuclear Engineering and Design 340, 62-67, 2018 | 9 | 2018 |
| Low cycle fatigue behavior and life evaluation of type 316L stainless steel at 700℃ DH Ha, SJ Kim, HY Lee, J Lee Trans. Korean Soc. Mech. Eng. A 46 (7), 655-662, 2022 | 8 | 2022 |
| Linear programming optimization of nuclear energy strategy with sodium-cooled fast reactors JW Lee, YH Jeong, YI Chang, SH Chang Nuclear Engineering and Technology 43 (4), 383-390, 2011 | 7 | 2011 |
| Issues and solutions for integrity of pressure vessels and piping subjected to long-term creep exposure in supercritical thermal plants HY Lee, J Lee Materials at High Temperatures 39 (6), 436-445, 2022 | 6 | 2022 |
| Cost benefit analysis of advanced nuclear fuel cycle using Linear Programming optimization J Lee, YI Chang, SH Chang Annals of Nuclear Energy 46, 116-120, 2012 | 6 | 2012 |
| Design of large-scale sodium thermal-hydraulic integral effect test facility, STELLA-2 J Lee, J Eoh, J Yoon, SK Son, H Kim Nuclear Engineering and Technology 54 (9), 3551-3566, 2022 | 5 | 2022 |
| High-temperature design of 700° C heat exchanger in a large scale high-temperature thermal energy storage performance test facility HY Lee, J Yoon, J Lee, J Eoh Pressure Vessels and Piping Conference 86151, V002T03A035, 2022 | 5 | 2022 |
| Heat transfer system design of sodium test facility STELLA-2 J Lee, J Eoh, J Yoon, SK Son, H Kim Annals of Nuclear Energy 191, 109930, 2023 | 4 | 2023 |
| Preliminary Assessment on Life Cycle of High Temperature Thermal Energy Storage System using Liquid Sodium H Kim, HJ Jeong, J Yoon, YH Shin, HY Lee, IS Jun, KS Yoon, JW Lee Transactions of the KNS Autumn Meeting, 2022 | 4 | 2022 |
| Heat transfer characteristics of redan structure in large-scale test facility STELLA-2 J Yoon, J Lee, H Kim, YB Lee, J Eoh Nuclear Engineering and Technology 53 (4), 1109-1118, 2021 | 4 | 2021 |
| Study on convective heat transfer correlations for sodium-to-sodium heat exchanger based on STELLA-1 experimental results J Hong, J Lee, J Eoh Nuclear Engineering and Design 371, 110963, 2021 | 4 | 2021 |
| Experimental study of the natural convection characteristics of finned-tube sodium-to-air heat exchanger J Lee, J Min, J Yoon, H Kim Journal of Mechanical Science and Technology 38 (4), 2055-2062, 2024 | 3 | 2024 |
| Feasibility study of a resistive-type sodium aerosol detector with ZnO nanowires for sodium-cooled fast reactors J Lee, DY Gam, KE Nam, SJ Cho, H Kim Nuclear Engineering and Technology 55 (7), 2373-2379, 2023 | 3 | 2023 |
| Dynamic data validation and reconciliation for improving the detection of sodium leakage in a sodium-cooled fast reactor S Park, J Yang, J Lee, G Heo Nuclear Engineering and Technology 55 (4), 1528-1539, 2023 | 3 | 2023 |
