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Jewhan Lee
Jewhan Lee
Korea atomic energy research institue
在 kaeri.re.kr 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
132023
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
132018
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
112020
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
92019
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
92018
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
92010
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
82018
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
72011
Low Cycle Fatigue Behavior and Life Evaluation of Type 316L Stainless Steel at 700 C
DH Ha, SJ Kim, HY Lee, J Lee
Trans. Korean Soc. Mech. Eng. A 46 (7), 655-662, 2022
62022
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
62012
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
52022
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
42022
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
42022
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
42021
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
42021
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
32022
Integrity Improvement of High-Temperature Pressure Boundary Components in the Creep Range by Applying Alternative Design Rules
HY Lee, J Lee, J Eoh
KSME A 45 (12), 1117-1126, 2021
32021
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
22023
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
22023
Similarity evaluation of the pump simulation loop in STELLA-2 for conservation of mechanical sodium pump characteristics
J Yoon, J Lee, J Eoh, H Kim, DE Kim
Nuclear Engineering and Technology 55 (1), 353-363, 2023
22023
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