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Hae-Yong Jeong

Observed names: H. Y. Jeong, H.-Y. Jeong, H.Y. Jeong, Hae-yong Jeong, Haeyong Jeong
Institution: Sejong University
ORCID: 0009-0001-9167-1410
Observed ORCID: 0009-0001-9167-1410
OpenAlex ID: A5110052275
A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles
2006 · Hae-Yong Jeong, Kwi-Seok Ha, et al. · International Journal of Heat and Mass Transfer · 52
Large-eddy simulation of thermal striping in unsteady non-isothermal triple jet
2011 · S. Chacko, Y.M. Chung, et al. · International Journal of Heat and Mass Transfer · 38
Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code
2005 · Hae-Yong Jeong, Kwi-Seok Ha, et al. · Nuclear Technology · 36
International benchmark on the natural convection test in Phenix reactor
2013 · D. Tenchine, D. Pialla, et al. · Nuclear Engineering and Design · 22
Simulation of the EBR-II Loss-of-Flow Tests Using the MARS Code
2010 · Kwi-Seok Ha, Hae-Yong Jeong, et al. · Nuclear Technology · 17
Evaluation of the conduction shape factor with a CFD code for a liquid–metal heat transfer in heated triangular rod bundles
2006 · Hae-yong Jeong, Kwi-seok Ha, et al. · Nuclear Engineering and Design · 17
A New Hyperparameter Tuning Framework for Regression Tasks in Deep Neural Network: Combined-Sampling Algorithm to Search the Optimized Hyperparameters
2024 · Nguyen Huu Tiep, Hae-Yong Jeong, et al. · Mathematics · 16
A Correlation for Single Phase Turbulent Mixing in Square Rod Arrays Under Highly Turbulent Conditions
2006 · Hae-Yong Jeong, Kwi-Seok Ha, et al. · Nuclear Engineering and Technology · 16
Development of the Matra-lmr-fb for Flow Blockage Analysis in a Lmr
2009 · Kwi-Seok Ha, Hae-Yong Jeong, et al. · Nuclear Engineering and Technology · 15
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Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.
2011 · Juan Carbajo, Hae-Yong Jeong, et al. · 14
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A comparative study of the MATRA-LMR-FB calculation with the SABRE result for the flow blockage accident in the sodium cooled fast reactor
2011 · W.P. Chang, K.S. Ha, et al. · Nuclear Engineering and Design · 13
A newly proposed data assimilation framework to enhance predictions for reflood tests
2022 · Nguyen Huu Tiep, Kyung-Doo Kim, et al. · Nuclear Engineering and Design · 11
Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code
2009 · H.-Y. Jeong, K.-S. Ha, et al. · Annals of Nuclear Energy · 11
Sodium Fast Reactor Safety and Licensing Research Plan – Volume II
2012 · USDOE National Nuclear Security Administration (NNSA), Jeffrey LaChance, et al. · 7
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Best estimate calculation and uncertainty quantification of sodium-cooled fast reactor using MARS-LMR code
2018 · Seok-Ju Kang, Hae-Yong Jeong, et al. · Annals of Nuclear Energy · 6
Wire-wrap Models for Subchannel Blockage Analysis
2004 · K. S. Ha, Hae-Yong Jeong, et al. · Nuclear Engineering and Technology · 6
Limiting conditions prediction using machine learning for loss of condenser vacuum event
2023 · Dong-Hun Shin, Moon-Ghu Park, et al. · Nuclear Engineering and Technology · 5
Validation of intermediate heat and decay heat exchanger model in MARS-LMR with STELLA-1 and JOYO tests
2016 · Chiwoong Choi, Kwiseok Ha, et al. · Nuclear Engineering and Design · 5
Comparison of the Decay Heat Removal Systems in the Kalimer-600 and Dsfr
2012 · Kwi-Seok Ha, Hae-Yong Jeong · Nuclear Engineering and Technology · 5
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Enhancement of Reflood Test Prediction by Integrating Machine Learning and Data Assimilation Technique
2024 · Nguyen Huu Tiep, Jong-Sung Kim, et al. · International Journal of Energy Research · 4
Machine Learning Applications and Uncertainty Quantification Analysis for Reflood Tests
2023 · Nguyen Huu Tiep, Kyung-Doo Kim, et al. · Applied Sciences · 4
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Application of a combined safety approach for the evaluation of safety margin during a Loss of Condenser Vacuum event
2021 · Dong-Hun Shin, Hae-Yong Jeong, et al. · Nuclear Engineering and Technology · 4
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Inherent Safety Analysis of the Kalimer Under a Lofa With a Reduced Primary Pump Halving Time
2011 · W.P. Chang, Y.M. Kwon, et al. · Nuclear Engineering and Technology · 4
A Study on Application of Warm Air Circulator by Using the Carbon Heating Element with Particle Type
2003 · Ki-Man Bae, K.S. Lee, et al. · 4
STAR-CCM+ simulation of debris bed formation in the unheated DEFCON-S experiment
2024 · Jeong-Hyeon Eom, In-Sik Ra, et al. · Annals of Nuclear Energy · 3
Works count: 68
Citation count: 347
H-index: 11
I10-index: 13
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