IMMAGINATION
VERSATILE
COMPUTATIONAL
SOLUTIONS
FOR NUCLEAR SYSTEMS AND SAFETY
- REALITY
A B O U T U S
Innovative computational methods are increasingly important in ensuring the safety and reliability of nuclear systems, due to their ability to accurately model and predict complex nuclear scenarios. These methods offer a promising outlook for cost savings, increased efficiency, and improved safety.
ESLAB at SNU advances technology in modeling & simulation by which scientists and engineers find new ways to tackle nuclear systems & safety challenges—challenges that cannot be addressed through traditional method alone. High Performance Computing (HPC) enables unprecedented large-scale numerical models for studying and simulating complex multi-physics problems in nuclear systems & safety that would otherwise be too expensive, too dangerous, or even impossible to study by direct experimentation.
With state-of-the-art computational modeling and predictive simulation capabilities, HPC reduces the risks and uncertainty that are often barriers to industry adopting new and innovative technologies. Our research efforts enable to save time and money and to significantly improve the breakthroughs and useful advances. Incorporating these capabilities, therefore, innovate nuclear systems & safety in efficiency, effectiveness, and reliability across all the activities including design, manufacturing, regulation, and policy making.
L A B O R A T O R Y N E W S
J A N 2 0 2 3 - P R E S E N T
KNS Best Paper Awards
Kyung Jun Park, Da Kyung Lee
2024. 5. 8
At the Spring Semester Korean Nuclear Society conference, ESLAB students Da-Kyung Lee and Kyung-Jun Park received the Best Paper Award. The titles of their papers are "Super-resolution of Wind Data and Compressed Utilization for Atmospheric Dispersion Modeling near Nuclear Power Plants: Based on Deep Learning and SVD" and "Dynamic Modeling of Free Piston Stirling Generator for Micro Nuclear Reactors," respectively. Congratulations to them!
BK Best Poster Award
Do Hyun Kim
2024. 1. 26
In our recent research progress, an adaptive resolution adjustment technique was adopted in our in-house CFD code, SOPHIA. Through these enhancements, our code has become capable of analyzing more complex phenomena at a reasonable computational cost. This is expected to make a significant contribution to nuclear safety analyses involving highly intricate scenarios. Thanks to his efforts, Do Hyun Kim won an excellence award at the BK21 Poster Competition. Congratulations!
Korea-Japan Bilateral Workshop on Nuclear Safety Information Exchange
2024. 1. 25
The 2024 Korea-Japan Bilateral Workshop was held in Jan. 15 to 17,
at Seoul National University, hosted by the FNC Technology. Our lab members had the opportunity to share their vision and progress on their research fields. Knowledge and intuition on nuclear safety were exchanged between two countries at a friendly atmosphere.
Prime Minister's Award
Eung Soo Kim
2023. 12. 28
The Ministry of Science and ICT hosted the 13th Nuclear Safety and Promotion Day on December 28th at the Westin Chosun Hotel in Seoul, in collaboration with the Ministry of Trade, Industry and Energy, and the Nuclear Safety and Security Commission. The event honored individuals for their contributions to nuclear and radiation safety, promotion, and export. Professor Eung Soo Kim was awarded the Prime Minister's Award for his work in developing multi-physics computational technology for simulating extreme nuclear disaster scenarios, contributing to nuclear safety technology. Celebrating a well-deserved recognition for outstanding achievements!
KNS Best Poster Award
Tae Hwan Kim
2023. 10. 26
In our recent research endeavor, we successfully crafted a cutting-edge library designed to yield corium properties based on input parameters such as temperature and the mass of individual constituents. This new corium property library not only facilitates simplified calculations at elevated temperatures but also promises to be a valuable database for diverse analyses necessitating corium properties. We are delighted to announce that Mr. Tae Hwan Kim has been honored with the KNS Best Poster award. Warmest congratulations on this well-deserved recognition!
Celerbration of
ESLAB 10th Anniversary
2022. 12. 16
Celerbration event of ESLAB 10th anniversary was held in Dec. 16.
Our proud alumni and many special guests were invited together and celerbrated our 10th anniversary. We had great dinner together with lots of talks and enjoyment. It was unforgentable time to recall our memories of the last 10 years. We wish the continued prosperity and development of our laboratory.
N E W P U B L I C A T I O N S
J A N 2 0 2 3 - P R E S E N T
Journal of Computational Physics 2024. 6. 1
Comparative Study of WCSPH, EISPH and Explicit Incompressible-Compressible SPH (EICSPH) for Multi-phase Flow with High Density Difference
Hee Sang Yoo et. al.
This study presents three Smoothed Particle Hydrodynamics (SPH) methods capable of handling high-density differences in violent incompressible multiphase flows. The conventional Weakly Compressible SPH (WCSPH) is reformulated into a quasi-Lagrangian framework based on Arbitrary Lagrangian–Eulerian (ALE) context. The Explicit Incompressible SPH (EISPH) method is extended to handle multiphase flows and reformulated in the ALE framework. The Explicit Incompressible-Compressible SPH (EICSPH) method, which can handle both compressible and incompressible phases, is developed by combining these two approaches in a fully explicit algorithm.
Nuclear Engineering & Technology 2024. xx. xx
Numerical Simulation on In-vessel Molten Corium Behavior with External Vessel Cooling using Smoothed Particle Hydrodynamics
Tae Hoon Lee et. al.
The in-vessel retention through external reactor vessel cooling (IVR-ERVC) strategy is a key management strategy for early termination of a nuclear severe accident that can threaten the integrity of the reactor vessel. To simulate the physical phenomena of the molten corium, the smoothed particle hydrodynamic (SPH) method is utilized in this study. The SPH method is a Lagrangian computational fluid dynamic (CFD) method that can simulate multi-fluid stratification, turbulence, natural circulation, radiative heat transfer, thermal ablation, and crust formation. The 1-D system analysis code can calculate the two-phase natural circulation of cooling water and the convective heat transfer on the external reactor vessel wall. These two simulation codes exchange the temperature and heat flux of the reactor vessel outer wall.
Powder Technology 2024. 8. 1
Integrated Internal-External Thermal Modeling for Packed Pebble Beds
Joong Young Seo et. al.
In this study, an integrated external-internal thermal DEM model is introduced in a GPU environment. The external model considers contact conduction and radiation, exhibiting accuracy validated against effective thermal conductivity (ETC) under packed bed conditions. The effective radiation range for a mono-sized packed bed is determined to be 3.5, providing accurate predictions of ETC. The internal model integrates FDM-based discretization to solve heat generation, heat conduction and thermal expansion. The model well predicts the temperature gradient of a sphere with partial heat generation. Additionally, preliminary analysis is conducted on the postulated heat generation of packed beds under a complete coolant-loss condition. The results reveal that fission-induced expansion may impact local porosity variations exceeding 2.5%. It is also observed that internally homogeneous models may overestimate heat transfer in packed beds, critical for safety. The model's accuracy and feasibility are demonstrated, providing insights for future research.
Nuclear Engineering and Technology 2024. 8. 24
Development of GPU-Paralleled multi-resolution techniques for Lagrangian-based CFD code in nuclear thermal-hydraulics and safety
Do Hyun Kim et. al.
A new paper has been published in the Nuclear Engineering and Technology (NET).
In this paper, a novel GPU-paralleled multi-resolution scheme was introduced within a smoothed particle hydrodynamics (SPH) framework. The presented model demonstrated an efficient computational performance capable of handling the large-scale calculations required for nuclear safety analysis. Do Hyun Kim made significant contributions to this publication.
(https://doi.org/10.1016/j.net.2024.02.008)
Journal of Hazardous Materials 2024. 1. 5
Comparative study on gradient-free optimization methods for inverse source-term estimation of radioactive dispersion from nuclear accidents
Siho Jang et. al.
A new paper has been published in the Journal of Hazardous Materials (JHM / IF: 14.222).
In this paper, a novel strategy to estimate the radionuclide source term in nuclear accidents was introduced, employing an ensemble-based framework that includes the Ensemble Kalman Inversion for the first time in the field of atmospheric dispersion. This model demonstrates promising potential for enhancing the results of inverse estimation and effectively applying high-performance computing technology in complex nonlinear physics systems. Major Siho Jang, a doctoral student sponsored by the Republic of Korea Army and first author of the study, along with Juryong Park as the second author, and Professor Eung Soo Kim as the corresponding author, made significant contributions to this publication.
(https://doi.org/10.1016/j.jhazmat.2023.132519)
Nuclear Engineering and Technology 2023. 5. 31
Numerical investigation of turbulent lid-driven flow using weakly compressible smoothed particle hydrodynamics CFD code with standard and dynamic LES models
Tae Soo Choi et. al.
A new paper has been published in the Nuclear Engineering and Technology (NET).
In this paper, a novel dynamic Vreman-based Large Eddy Simulation (LES) model was introduced within a weakly-compressible SPH framework. The proposed model demonstrates promising potential studying high-Reynolds flow dynamics for nuclear safety. Dr. Tae Soo Choi made a big effort on this publication.
(https://doi.org/10.1016/j.net.2023.05.026)
Physics of Plasma 2023. 5. 31
Smoothed particle hydrodynamics method for pinch plasma simulation with non-ideal MHD model
Su-San Park et. al.
A new paper has been published in the Physics of Plasmas (POP).
In this paper, a novel non-ideal magnetohydrodynamics (MHD) model was introduced within a smoothed particle hydrodynamics (SPH) framework. The proposed model demonstrates promising potential for studying complex pinch plasma phenomena. Dr. Su-San Park made a big effort on this publication.
(https://doi.org/10.1063/5.0138221)
Nuclear Engineering and Design 2023. 2. 28
Lagrangian Computational Fluid Dynamics for Nuclear Thermal-Hydraulics and Safety
Young Beom Jo et. al.
Lagrangian numerical methods have gained significant attention in recent years due to advancements in computational environments. These methods represent the domain of interest using a finite number of particles that carry individual properties and solve discretized equations over adjacent particles. Lagrangian CFD methods excel over traditional grid-based methods in handling free surfaces, multi-phase systems, and complex boundary deformations. This flexibility makes them suitable for nuclear thermal-hydraulics and safety problems where traditional methods struggle. However, improvements are needed in computational cost, accuracy, stability, and adaptivity. This paper reviews the progress and challenges of Lagrangian CFD methods, particularly focusing on smoothed particle hydrodynamics (SPH).
International Journal of Heat and Mass Transfer 2023. 2. 28
Modeling and Analysis of Salt-Convection Effect on Oxide Reduction Process for Uranium Oxides
Jin Woo Kim et. al.
Oxygen ion transport via molten salt continuum is crucial in the electrochemical reduction of uranium oxides. During electrolysis, oxygen ion concentration evolves from a porous metallic layer to the open bulk salt. Despite its importance, the effect of controlled salt movement on process throughput was underexplored. To capture oxygen ion transport phenomena, a multidimensional reduction model using smoothed particle hydrodynamics (SPH) was combined with the advection-diffusion model. The study quantified reduction time of a pelletized-fuel bed with respect to key design parameters, showing that salt convection effectively removes oxygen ion products and accelerates the reduction process. The developed SPH-based framework allowed for multi-physics analysis, aiding in the evaluation of reactant material configurations.
International Journal of Heat and Mass Transfer 2023. 2. 28
Modeling and Analysis of Salt-Convection Effect on Oxide Reduction Process for Uranium Oxides
Jin Woo Kim et. al.
Oxygen ion transport via molten salt continuum is crucial in the electrochemical reduction of uranium oxides. During electrolysis, oxygen ion concentration evolves from a porous metallic layer to the open bulk salt. Despite its importance, the effect of controlled salt movement on process throughput was underexplored. To capture oxygen ion transport phenomena, a multidimensional reduction model using smoothed particle hydrodynamics (SPH) was combined with the advection-diffusion model. The study quantified reduction time of a pelletized-fuel bed with respect to key design parameters, showing that salt convection effectively removes oxygen ion products and accelerates the reduction process. The developed SPH-based framework allowed for multi-physics analysis, aiding in the evaluation of reactant material configurations.
Experiments in Fluids 2023. 2. 28
Deep Learning-based Spatial Refinement Method for Robust High Resolution PIV Analysis
Jun Sung Choi et. al.
In this study, a deep learning-based spatial refinement method was proposed to provide robust high-resolution velocity fields for particle image velocimetry (PIV) analysis. The architecture of the convolutional neural network (CNN)-based optical flow model, FlowNet2, was modified to handle small-scale flows by training with subdomains of particle image pairs. The modified deep learning model was trained with synthetic datasets replicating various PIV conditions. It was then incorporated into a correlation-based spatial refinement approach for robust multiscale flow measurement. Validation using synthetic particle images and real PIV images in turbulent flow demonstrated the method's accuracy and robustness under various conditions. This CNN-based approach outperformed classic methods by capturing high-resolution velocity fields without the need for averaging, smoothening, or further parameter tuning.
M E M B E R S
S I N C E 2 0 1 2
Professor
Prof. Eung Soo Kim
· 2024 ~ Present Executive Editor, Nuclear Engineering and Technology (NET)
· 2024 ~ Present Associate Editor, Journal of Nuclear Science & Technology (JNST)
· 2023 ~ 2024 Department Chair, Nuclear Engineering, SNU, South Korea
· 2021 ~ Present Professor, Seoul National University(SNU), South Korea
· 2018 Visiting Professor, University of Michigan, USA
· 2016 ~ 2020 Associate Professor, Seoul National University, South Korea
· 2012 ~ 2015 Assistant Professor, Seoul National University, South Korea
· 2009 ~ 2011 Staff Scientist/Engineer, Idaho National Laboratory, USA
· 2006 ~ 2009 Postdoc, Idaho National Laboratory, USA
· 2006 Postdoc, KAIST, South Korea
· 2006 Ph.D., KAIST, South Korea
· 2012 ~ 2015 Assistant Professor, Seoul National University, South Korea
· 2009 ~ 2011 Staff Scientist/Engineer, Idaho National Laboratory, USA
· 2006 ~ 2009 Postdoc, Idaho National Laboratory, USA
· 2006 Postdoc, KAIST, South Korea
· 2006 Ph.D., KAIST, South Korea
Research Scholars
Young Beom Jo, Ph.D
Research Professor
paul406@snu.ac.kr
#SPH, #DEM. #Multi-phase,
#Severe Accident, #Granular Micro Reactor
Postdoctoral Researchers
Hee Sang Yoo, Ph.D
Postdoctoral Researcher
yhs0365@snu.ac.kr
#SPH, #Surface Tension, #Microfluidics, #ALE, #Axisymmetric
Ph.D Students
Jin Hyun Kim
uhaha118@snu.ac.kr
#SPH, #ASPH,
#Shockwave, #Explosion, #Granular Micro Reactor
#SPH, #ASPH,
#Shockwave, #Explosion, #Granular Micro Reactor
Yelyn Ahn
zks1124@snu.ac.kr
#SPH, #Bubble Dynamics,
#Phase-Field-Model, #HPC, #GPU
#SPH, #Bubble Dynamics,
#Phase-Field-Model, #HPC, #GPU
Tae Hoon Lee
zrkanl0521@snu.ac.kr
#SPH #Fluid Structure Interaction
#IVR-ERVC
Hoon Chae
Hoon Chae
georgechae@snu.ac.kr
#SPH, #DEM, #Boiling,
#Non-spherical, #Granular Micro Reactor
#SPH, #DEM, #Boiling,
#Non-spherical, #Granular Micro Reactor
Jin Woo Kim
wlsdn1362@snu.ac.kr
##SPH #Structural Anaysis #FSI #Severe Accident
Jun Sung Choi
cjs8088@snu.ac.kr
#Flow Visualization, #Machine Learning,
#PIV, #MCCI
#Flow Visualization, #Machine Learning,
#PIV, #MCCI
Juryong Park
itts9904@snu.ac.kr
#Lagrangian Stochastic Dispersion, #Radioactive Dispersion, #Evacuation, #GIS, #SPH
Do Hyun Kim
hyen0929@snu.ac.kr
#SPH, #Particle Split/Merge,
#Multi-resolution, #Evacuation, #CFD
Joo Hyung Lee
alsdktkfkdgody@snu.ac.kr
#SPH, #Generative Design
Siho Jang
siho.jang86@gmail.com
#Dispersion, #Back-trajectory, # Source-Receptor Model
#Dispersion, #Back-trajectory, # Source-Receptor Model
Kyu Byung Lee
xxxx@snu.ac.kr
#Severe Accident, #Nuclear Safety
#Severe Accident, #Nuclear Safety
Kyung Jun Park
815rudwns@gmail.com
#Micro-reactor #Marine Propulsion
Da Kyoung Lee
dkyoun.g@snu.ac.kr
#Meteorological data #Deep Learning
#Super-resolution
MS Students
Joong Yeong Seo
joongyeongseo@snu.ac.kr
#SPH #DEM #PBR
Sang Hoon Lim
jameslim@snu.ac.kr
#RHRS #GAMMA
Min Jae Kim
minja2@snu.ac.kr
#MCCI #SPH
Ju Bin Kim
kimjubin1@snu.ac.kr
#FCI #Steam Explosion #Severe Accident
Min Chan Kwon
ksn5014@snu.ac.kr
#FCI #Corium Spreading #Severe Accident
Jiho Kim
kjiho0403@snu.ac.kr
#Lattice Boltzmann Method
Su Hyun Kim
shy0519@snu.ac.kr
#TBD
Kyung Dong Lim
ikd2001@snu.ac.kr
#TBD
Sohyeon Ahn
ahn19@snu.ac.kr
#TBD
Jihyun Lee
ss10248s@snu.ac.kr
#Dispersion, #Evacuation
Hojin Jang
hojin9908@snu.ac.kr
#TBD
Injae Kim
rladlswo678@snu.ac.kr
#TBD
Undergraduate Students
Byeong Hyeon Ji
jihanjin2@snu.ac.kr
#TBD
Administrator
Eui Nae Cho
shan77@snu.ac.kr
#Adminitration
#Adminitration
Alumni
Min Young Park (Ph.D)
Korea Atomic Energy Research Institute (KAERI)
Senior Researcher
Senior Researcher
Min Seop Song (Ph.D)
Hanyang University, Korea
(Nuclear Eng. Dept.)
Assistant Professor
Young Beom Jo (Ph.D)
Seoul National University
(SNU)
Research Professor
Jae Soon Kim (Ph.D)
Korea Institute of Nuclear Safety
(KINS)
Senior Researcher
Serin Shin (M.S)
Korea Atomic Energy Research Institute (KAERI)
Researcher
Researcher
Ji Hyun Seong (M.S)
Korea Advanced Institute of Science and Technology, Korea
(KAIST)
Assistant Professor
Dokyun Lim (M.S)
Korea Institute of Nuclear Safety, Korea
(KINS)
Staff Researcher
(KINS)
Staff Researcher
So-Hyun Park (Ph.D)
Korea Atomic Energy Research Institute
(KAERI)
Senior Researcher
(KAERI)
Senior Researcher
Hae Yoon Choi (Ph.D)
SAMSUNG Electronics
(SAMSUNG)
Senior Researcher
Il Woong Park (Research Prof.)
Inha University
(Mechnanical Engineering Dept.)
Assistant Professor
Jongsung Chi (M.S.)
Republic of Korea Navy
(ROKN)
Lieutenant Commander
Tae Soo Choi (Ph.D)
Korea Institute of Nuclear Safety
(KINS)
Senior Researcher
Su San Park (Ph.D)
SAMSUNG Electronics
(SAMSUNG)
Senior Researcher
Hee Sang Yoo (Ph.D)
Commissariat à l'énergie atomique
(CEA, France)
Postdoctoral Researcher
R E S E A R C H E S
Solving Complex Problems for Nuclear Engineering with Modern Computational Science and Technology
High Performance Computing (HPC) enables unprecedented large-scale numerical models for studying and simulating complex multi-physics problems in nuclear systems & safety that would otherwise be too expensive, too dangerous, or even impossible to study by direct experimentation. Incorporating these capabilities can innovate nuclear systems & safety in efficiency, effectiveness, and reliability across all the activities from design & manufacturing to regulation & policy making.
P R O J E C T S
G O V E R N M E N T
- 2024-2029
- 차세대 고온원자력 시스템 융복합 인력양성센터 (한국연구재단) [참여]
- 2024-2026
- 피동잔열제거계통 검증 및 성능평가 (한국원자력안전재단) [위탁]
- 2024-2026
- 경수형 SMR 계통 안전성 평가 규제기반기술 개발(한국원자력안전재단) [주관]
- 2024-2029
- 부유체 운동을 고려한 부유식 SMR 발전플랫폼 성능평가(한국선박해양연구소) [위탁]
- 2022-2024
- 선원항 평가를 위한 역추적모델 개발 (한국원자력안전기술원) [위탁]
- 2021-2026
- 고성능 GPU 컴퓨팅 및 입자법 기반의 차세대 원자력 중대사고 전산모의 핵심기술 개발 (한국연구재단) [주관]
- 2021-2026
- 격납건물 고위험 중요도 중대사고 현상 모듈 개발 (한국원자력안전재단) [참여]
I N D U S T R Y
- 2020-2022
- 정찰 및 전투용 무인잠수정을 위한 마이크로 히트파이프 원자로 기반의 배터리 개념개발 및 개념설계 (대우조선) [주관]
- 2022-TBD
- 인쇄기판형 열교환기 설계기술 개발 [주관]
L A B - I N T E R N A L
- 2022. 3 ~
- PCHE 및 열에너지 하베스팅을 이용한 CVCS 소형화 기술 개발
- 2022. 3 ~
- 고효율 저탄소 원자력-가스 복합 시스템 기술 개발
- 2022. 1 ~
- 도심 내 속도 분포 및 오염물 확산 고속 예측 기술 개발
- 2022. 1 ~
- 마이크로 원자로 배터리를 위한 디지털 트윈 기술 기술 개발
- 2021. 3 ~
- 입자형 노심 기반의 마이크로 원자로 배터리 기술 개발
- 2021. 9 ~
- 열에너지 하베스팅을 이용한 지능형 피동 수소 제거기 개발
P U B L I C A T I O N S
Seo, Joong Young, Eung Soo Kim, and Young Beom Jo. "Integrated internal-external thermal modeling for packed pebble beds." Powder Technology 443 (2024). (https://doi.org/10.1016/j.powtec.2024.119928)
Jung, Min Ki, et al. "SPRAY: A smoothed particle radiation hydrodynamics code for modeling high intensity laser-plasma interactions." Journal of Computational Physics 508 (2024). (https://doi.org/10.1016/j.jcp.2024.113000)
Yoo, Hee Sang, Young Beom Jo, and Eung Soo Kim. "Comparative study of WCSPH, EISPH and explicit incompressible-compressible SPH (EICSPH) for multi-phase flow with high density difference." Journal of Computational Physics 506 (2024). (https://doi.org/10.1016/j.jcp.2024.112930)
Lee, Tae Hoon, et al. "Numerical Simulation on In-Vessel Molten Corium Behavior with External Vessel Cooling using Smoothed Particle Hydrodynamics." Nuclear Engineering and Technology (2024). (https://doi.org/10.1016/j.net.2024.05.003)
Kim, Do Hyun, et al. "Development of GPU-Paralleled multi-resolution techniques for Lagrangian-based CFD code in nuclear thermal-hydraulics and safety." Nuclear Engineering and Technology (2024). (https://doi.org/10.1016/j.net.2024.02.008)
Jang, Siho, et al. "Comparative study on gradient-free optimization methods for inverse source-term estimation of radioactive dispersion from nuclear accidents." Journal of hazardous materials 461 (2024): 132519. (https://doi.org/10.1016/j.jhazmat.2023.132519)
Park, Eui-Kyun, et al. "Failure simulation of nuclear pressure vessel under LBLOCA scenarios." Nuclear Engineering and Technology (2024). (https://doi.org/10.1016/j.net.2024.02.049)
Moon, Hyeongi, et al. "In-depth investigation of natural convection thermal characteristics of BALI experiment through Eulerian computational fluid dynamics code and comparison with Lagrangian code." Nuclear Engineering and Technology 56.1 (2024). (https://doi.org/10.1016/j.net.2023.08.015)
Kim, Jin-Woo, et al. "Modelling and analysis of salt-convection effect on oxide reduction process for uranium oxides using smoothed particle hydrodynamics." International Journal of Heat and Mass Transfer 206 (2023): 123965 (https://doi.org/10.1016/j.ijheatmasstransfer.2023.123965)
Choi, Tae Soo, and Eung Soo Kim. "Numerical investigation of turbulent lid-driven flow using weakly compressible smoothed particle hydrodynamics CFD code with standard and dynamic LES models." Nuclear Engineering and Technology (2023). (https://doi.org/10.1016/j.net.2023.05.026)
Park, Su-San, et al. "Smoothed particle hydrodynamics method for pinch plasma simulation with non-ideal MHD model." Physics of Plasmas 30.5 (2023). (https://doi.org/10.1063/5.0138221)
Choi, Jun Sung, Eung Soo Kim, and Jee Hyun Seong. "Deep learning-based spatial refinement method for robust high-resolution PIV analysis." Experiments in Fluids 64.3 (2023): 45. (https://doi.org/10.1007/s00348-023-03595-x)
Young Beom Jo, So-Hyun Park, Eung Soo Kim, Lagrangian computational fluid dynamics for nuclear Thermal-Hydraulics & safety, Nuclear Engineering and Design, Volume 405, (2023). (https://doi.org/10.1016/j.nucengdes.2023.112228)
Yoo, Hee Sang, et al. "A Simple Eulerian‐Lagrangian Weakly Compressible Smoothed Particle Hydrodynamics (EL‐WCSPH) Method for Fluid Flow and Heat Transfer." International Journal for Numerical Methods in Engineering (2022). (https://doi.org/10.1002/nme.7148)
Kim, Jin-Woo, et al. "Smoothed particle hydrodynamics modeling and analysis of oxide reduction process for uranium oxides." Chemical Engineering Science 261 (2022): 117974. (https://doi.org/10.1016/j.ces.2022.117974)
Jo, Young Beom, et al. "GPU-based SPH-DEM Method to Examine the Three-Phase Hydrodynamic Interactions between Multiphase Flow and Solid Particles." International Journal of Multiphase Flow (2022): 104125. (https://doi.org/10.1016/j.ijmultiphaseflow.2022.104125)
Yoo, Hee Sang, et al. "Effect of wettability on the water entry of spherical projectiles: Numerical analysis using smoothed particle hydrodynamics." AIP Advances 12.3 (2022): 035014. (https://doi.org/10.1063/5.0072710)
Song, Min Seop, et al. "Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1. 5 code: CFD-aided estimation of natural circulation flow rate." Nuclear Engineering and Technology 54.1 (2022): 72-83. (https://doi.org/10.1016/j.net.2021.07.037)
Choi, Hae Yoon, Hoon Chae, and Eung Soo Kim. "Numerical simulation on jet breakup in the fuel-coolant interaction using smoothed particle hydrodynamics." Nuclear Engineering and Technology 53.10 (2021): 3264-3274. (https://doi.org/10.1016/j.net.2021.04.021)
Park, Su-San, and Eung Soo Kim. "Jamming probability of granular flow in 3D hopper with shallow columns: DEM simulations." Granular Matter 22.4 (2020): 1-13. (https://doi.org/10.1007/s10035-020-01050-w)
Song, Minseop, Jae-Ho Jeong, and Eung Soo Kim. "Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics." Nuclear Engineering and Design 370 (2020): 110904. (https://doi.org/10.1016/j.nucengdes.2020.110904)
Jo, Y.B, Park, J.R., Kim, E.S.*, Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics, Nuclear Engineering and Technology, 2020. (https://doi.org/10.1016/j.net.2020.07.039)
Park, S.H., Jo, Y.B., Kim, E.S.*, Development of Multi-GPU-Based Smoothed Particle Hydrodynamics Code for Nuclear Thermal-hydraulics and Safety: Potential and Challenges, Frontiers in Energy Research, Vol. 8, 2020. (https://doi.org/10.3389/fenrg.2020.00086)
Song, M.S., J.H., Jeong, Kim, E.S.*, Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD Analysis, Annals of Nuclear Energy, Vol. 147, 2020.(https://doi.org/10.1016/j.anucene.2020.107653)
Seong, J.H., Song, M.S., Nunez, D, Manera, A., Kim, E.S.*, Velocity Refinement of PIV using Global Optical Flow, Experiments in Fluids, Vo. 60, 2019. (https://link.springer.com/article/10.1007/s00348-019-2820-4)
Yoo, H.S., Kim, E.S.*, Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas, Annals of Nuclear Energy, Vol. 132, pp. 108-118, 2019. (https://doi.org/10.1016/j.anucene.2019.04.018)
Lim, D.K., Kim, E.S.*, Song, M.S., Chae, H., Topology Optimization on Vortex-type Passive Fludic Diode for Advanced Nuclear Reactors, Nuclear Engineering and Technology, Vol. 51, 2019. (https://doi.org/10.1016/j.net.2019.03.018)
Song, M.S., Jeong, J.H., Kim, E.S.*, Numerical Investigation on Vortex Behavior in Wire-wrapped Fuel Assembly for Sodium Fast Reactor, Nuclear Engineering and Technology, Vol. 51, pp 665-675, 2019. (https://doi.org/10.1016/j.net.2018.12.012)
Jo, Y.B., Park, S.H., Choi, H.Y., Jung, H.W., Kim, Y.J., Kim, E.S.*, SOPHIA: Development of Lagrangian-based CFD Code for Nuclear Thermal-Hydraulics and Safety Applications, Annals of Nuclear Energy, Vol. 124, pp. 132-149, 2019. (https://doi.org/10.1016/j.anucene.2018.09.005)
Park, S.H., Choi, T.S., Choi, H.Y., Jo, Y.B., Kim, E.S.*, Simulation of a Laboratory-scale Experiment for Wave Propagation and Interaction with a Structure of Undersea Topography near a Nuclear Power Plant using a Divergence-Free SPH, Annals of Nuclear Energy, Vol. 122, pp. 340-351, 2018. (https://doi.org/10.1016/j.anucene.2018.08.045)
Park, M.Y., Kim, E.S.*, Analysis of tritium behaviors on VHTR and forward osmosis integration system, Nuclear Engineering and Design, Vol. 338, pp. 34-51, 2018. (https://doi.org/10.1016/j.nucengdes.2018.07.030)
Shin, S.R., Jeong, J.H., Lim, D.K., Kim, E.S.*, Design of SFR fluidic diode axial port using topology optimization, Nuclear Engineering and Design, Vol. 338, pp. 63-73, 2018. (https://doi.org/10.1016/j.nucengdes.2018.07.028)
Lim, D.K., Park, Y.J., Kim, H.D., Kim, E.S.*,CFD-based shape optimization on cross-section of monoblock fusion divertor cooling channel for minimizing local heat flux, Fusion Engineering and Design, Vol. 136, pp. 1100-1105, 2018. (https://doi.org/10.1016/j.fusengdes.2018.04.077)
Ham, T.K., D.J., Arcilesi, I.H., Kim, Sun, Xiaodong, Christensen, R.N., Oh, C.H., Kim, E.S., Computational fluid dynamics analysis of the initial stages of a VHTR air-ingress accident using a scaled-down model, Nuclear Engineering and Design, Vol. 300, pp. 517-529, 2016. (https://doi.org/10.1016/j.nucengdes.2016.02.011)
Song, M.S., Park, S.H., Kim, E.S.*, Particle image velocimetry measurement of 2-dimensional velocity field around twisted tape, Fusion Engineering and Design, Vol. 109, pp. 596-601, 2016. (https://doi.org/10.1016/j.fusengdes.2016.02.039)
Park, M.Y., Song, M.S., Kim, E.S.*, Development of tritium permeation model for printed circuit heat exchanger, Annals of Nuclear Energy, Vol. 98, pp. 166-177, 2016. (https://doi.org/10.1016/j.anucene.2016.08.001)
Kim, J.S., Kim, B.J., Kim, E.S.*, Oh, C.H., Experimental Study on Fundamental Phenomena in HTGR Small Break Air-Ingress Accident, Annals of Nuclear Energy,Vol. 87, pp. 145-156, 2016. (https://doi.org/10.1016/j.anucene.2015.08.012)
Lee, Y.G., Park, I.W., Park, G.C., Kim, E.S*, and Lee, D.W, Reduction of Circulation Power for Helium-Cooled Fusion Reactor Blanket using Additive CO2 gas, Fusion Engineering and Design, Vol. 100, pp. 436-442, 2015. (https://doi.org/10.1016/j.fusengdes.2015.07.010)
Park, M.Y., Shin, S.R., Kim, E.S.*, Effective Energy Management by Combining Gas Turbine Cycles and Forward Osmosis Desalization Process, Applied Energy, Vol. 154, pp. 51-61, 2015. (https://doi.org/10.1016/j.apenergy.2015.04.119)
Park, M.Y., Kim, E.S.*, Development of semi-empirical model for tritium permeation under non-uniform temperature distribution at heat exchanger tube wall, Annals of Nuclear Energy, Vol. 75, pp. 413-420, 2015. (https://doi.org/10.1016/j.anucene.2014.08.044)
Song, M.S. Choi, H.Y., Sung, J.H., Kim, E.S*., Matching index of refraction of transparent 3D printing models for flow visualization, Nuclear Engineering and Design, Vol. 284, pp. 185-191, 2015. (https://doi.org/10.1016/j.nucengdes.2014.12.019)
Park, M.Y., and Kim, E.S.*, Thermodynamic Evaluation on the Integrated System of VHTR and Forward Osmosis Desalination Process, Desalination, vo. 337, pp. 117-126, 2014. (https://doi.org/10.1016/j.desal.2013.11.023)
Yoon, S.J., Kim, E.S., and Sabharwall, P., Numerical Study on Crossflow Printed Circuit Heat Exchanger for Advanced Small Modular Reactor, International Journal of Heat and Mass Transfer, vol. 70, pp. 250-263, 2013. (https://doi.org/10.1016/j.ijheatmasstransfer.2013.10.079)
Chang H. Oh, Eung Soo Kim, Isothermal Air-Ingress Validation Experiments, Nuclear Technology, Vol. 181, pp. 68-80 (Recommended for Publication in Nuclear Technology from NURETH-14), 2013. (https://doi.org/10.13182/NT13-A15757)
Su-Jong Yoon, Min-Seup Song, Il-Woong Park, Goon-Cherl Park, and Eung Soo Kim*, Assessment of COMSOL Capability to Analyze Thermal-Hydraulic Characteristic of Korean Helium Cooled Test Blanket, SOFA, Fusion Engineering and Design, Vol. 88, pp. 2240-2243, 2013. (https://doi.org/10.1016/j.fusengdes.2013.02.016)
Jeong-Hun Lee, Su-Jong Yoon, Eung Soo Kim, and Goon-Cherl Park, CFD Analysis and Assessment for Cross Flow Phenomena in VHTR Prismatic Core, Heat Transfer Enginnering, vol. 35, pp. 11-12, 2014. (https://doi.org/10.1080/01457632.2013.863566)
Piyush Sabharwall, Eung Soo Kim, Mike Patterson, Evaluation Methodology for Advance Heat Exchanger Concepts Using Analytical Hierachy Process, Nuclear Engineering and Design, Vol. 248, pp. 108-116, 2012. (https://doi.org/10.1016/j.nucengdes.2012.03.030)
Chang H. Oh, Eung S. Kim, Conceptual Study on Air Ingress Mitigation for VHTRs, Nuclear Engineering & Deisgn, Vol. 250, pp. 448-464, 2012. (https://doi.org/10.1016/j.nucengdes.2012.04.021)
Chang H. OH, Eung S. Kim, Natural Circulation Patterns in the VHTR Air-ingress Accident and Related Issues, Nuclear Engineering Design, Vol. 249, pp. 228-236, 2012. (https://doi.org/10.1016/j.nucengdes.2011.09.031)
Jo, Y.B, Park, J.R., Kim, E.S.*, Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics, Nuclear Engineering and Technology, 2020. (https://doi.org/10.1016/j.net.2020.07.039)
Park, S.H., Jo, Y.B., Kim, E.S.*, Development of Multi-GPU-Based Smoothed Particle Hydrodynamics Code for Nuclear Thermal-hydraulics and Safety: Potential and Challenges, Frontiers in Energy Research, Vol. 8, 2020. (https://doi.org/10.3389/fenrg.2020.00086)
Song, M.S., J.H., Jeong, Kim, E.S.*, Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD Analysis, Annals of Nuclear Energy, Vol. 147, 2020.(https://doi.org/10.1016/j.anucene.2020.107653)
Seong, J.H., Song, M.S., Nunez, D, Manera, A., Kim, E.S.*, Velocity Refinement of PIV using Global Optical Flow, Experiments in Fluids, Vo. 60, 2019. (https://link.springer.com/article/10.1007/s00348-019-2820-4)
Yoo, H.S., Kim, E.S.*, Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas, Annals of Nuclear Energy, Vol. 132, pp. 108-118, 2019. (https://doi.org/10.1016/j.anucene.2019.04.018)
Lim, D.K., Kim, E.S.*, Song, M.S., Chae, H., Topology Optimization on Vortex-type Passive Fludic Diode for Advanced Nuclear Reactors, Nuclear Engineering and Technology, Vol. 51, 2019. (https://doi.org/10.1016/j.net.2019.03.018)
Song, M.S., Jeong, J.H., Kim, E.S.*, Numerical Investigation on Vortex Behavior in Wire-wrapped Fuel Assembly for Sodium Fast Reactor, Nuclear Engineering and Technology, Vol. 51, pp 665-675, 2019. (https://doi.org/10.1016/j.net.2018.12.012)
Jo, Y.B., Park, S.H., Choi, H.Y., Jung, H.W., Kim, Y.J., Kim, E.S.*, SOPHIA: Development of Lagrangian-based CFD Code for Nuclear Thermal-Hydraulics and Safety Applications, Annals of Nuclear Energy, Vol. 124, pp. 132-149, 2019. (https://doi.org/10.1016/j.anucene.2018.09.005)
Park, S.H., Choi, T.S., Choi, H.Y., Jo, Y.B., Kim, E.S.*, Simulation of a Laboratory-scale Experiment for Wave Propagation and Interaction with a Structure of Undersea Topography near a Nuclear Power Plant using a Divergence-Free SPH, Annals of Nuclear Energy, Vol. 122, pp. 340-351, 2018. (https://doi.org/10.1016/j.anucene.2018.08.045)
Park, M.Y., Kim, E.S.*, Analysis of tritium behaviors on VHTR and forward osmosis integration system, Nuclear Engineering and Design, Vol. 338, pp. 34-51, 2018. (https://doi.org/10.1016/j.nucengdes.2018.07.030)
Shin, S.R., Jeong, J.H., Lim, D.K., Kim, E.S.*, Design of SFR fluidic diode axial port using topology optimization, Nuclear Engineering and Design, Vol. 338, pp. 63-73, 2018. (https://doi.org/10.1016/j.nucengdes.2018.07.028)
Lim, D.K., Park, Y.J., Kim, H.D., Kim, E.S.*,CFD-based shape optimization on cross-section of monoblock fusion divertor cooling channel for minimizing local heat flux, Fusion Engineering and Design, Vol. 136, pp. 1100-1105, 2018. (https://doi.org/10.1016/j.fusengdes.2018.04.077)
Ham, T.K., D.J., Arcilesi, I.H., Kim, Sun, Xiaodong, Christensen, R.N., Oh, C.H., Kim, E.S., Computational fluid dynamics analysis of the initial stages of a VHTR air-ingress accident using a scaled-down model, Nuclear Engineering and Design, Vol. 300, pp. 517-529, 2016. (https://doi.org/10.1016/j.nucengdes.2016.02.011)
Song, M.S., Park, S.H., Kim, E.S.*, Particle image velocimetry measurement of 2-dimensional velocity field around twisted tape, Fusion Engineering and Design, Vol. 109, pp. 596-601, 2016. (https://doi.org/10.1016/j.fusengdes.2016.02.039)
Park, M.Y., Song, M.S., Kim, E.S.*, Development of tritium permeation model for printed circuit heat exchanger, Annals of Nuclear Energy, Vol. 98, pp. 166-177, 2016. (https://doi.org/10.1016/j.anucene.2016.08.001)
Kim, J.S., Kim, B.J., Kim, E.S.*, Oh, C.H., Experimental Study on Fundamental Phenomena in HTGR Small Break Air-Ingress Accident, Annals of Nuclear Energy,Vol. 87, pp. 145-156, 2016. (https://doi.org/10.1016/j.anucene.2015.08.012)
Lee, Y.G., Park, I.W., Park, G.C., Kim, E.S*, and Lee, D.W, Reduction of Circulation Power for Helium-Cooled Fusion Reactor Blanket using Additive CO2 gas, Fusion Engineering and Design, Vol. 100, pp. 436-442, 2015. (https://doi.org/10.1016/j.fusengdes.2015.07.010)
Park, M.Y., Shin, S.R., Kim, E.S.*, Effective Energy Management by Combining Gas Turbine Cycles and Forward Osmosis Desalization Process, Applied Energy, Vol. 154, pp. 51-61, 2015. (https://doi.org/10.1016/j.apenergy.2015.04.119)
Park, M.Y., Kim, E.S.*, Development of semi-empirical model for tritium permeation under non-uniform temperature distribution at heat exchanger tube wall, Annals of Nuclear Energy, Vol. 75, pp. 413-420, 2015. (https://doi.org/10.1016/j.anucene.2014.08.044)
Song, M.S. Choi, H.Y., Sung, J.H., Kim, E.S*., Matching index of refraction of transparent 3D printing models for flow visualization, Nuclear Engineering and Design, Vol. 284, pp. 185-191, 2015. (https://doi.org/10.1016/j.nucengdes.2014.12.019)
Park, M.Y., and Kim, E.S.*, Thermodynamic Evaluation on the Integrated System of VHTR and Forward Osmosis Desalination Process, Desalination, vo. 337, pp. 117-126, 2014. (https://doi.org/10.1016/j.desal.2013.11.023)
Yoon, S.J., Kim, E.S., and Sabharwall, P., Numerical Study on Crossflow Printed Circuit Heat Exchanger for Advanced Small Modular Reactor, International Journal of Heat and Mass Transfer, vol. 70, pp. 250-263, 2013. (https://doi.org/10.1016/j.ijheatmasstransfer.2013.10.079)
Chang H. Oh, Eung Soo Kim, Isothermal Air-Ingress Validation Experiments, Nuclear Technology, Vol. 181, pp. 68-80 (Recommended for Publication in Nuclear Technology from NURETH-14), 2013. (https://doi.org/10.13182/NT13-A15757)
Su-Jong Yoon, Min-Seup Song, Il-Woong Park, Goon-Cherl Park, and Eung Soo Kim*, Assessment of COMSOL Capability to Analyze Thermal-Hydraulic Characteristic of Korean Helium Cooled Test Blanket, SOFA, Fusion Engineering and Design, Vol. 88, pp. 2240-2243, 2013. (https://doi.org/10.1016/j.fusengdes.2013.02.016)
Jeong-Hun Lee, Su-Jong Yoon, Eung Soo Kim, and Goon-Cherl Park, CFD Analysis and Assessment for Cross Flow Phenomena in VHTR Prismatic Core, Heat Transfer Enginnering, vol. 35, pp. 11-12, 2014. (https://doi.org/10.1080/01457632.2013.863566)
Piyush Sabharwall, Eung Soo Kim, Mike Patterson, Evaluation Methodology for Advance Heat Exchanger Concepts Using Analytical Hierachy Process, Nuclear Engineering and Design, Vol. 248, pp. 108-116, 2012. (https://doi.org/10.1016/j.nucengdes.2012.03.030)
Chang H. Oh, Eung S. Kim, Conceptual Study on Air Ingress Mitigation for VHTRs, Nuclear Engineering & Deisgn, Vol. 250, pp. 448-464, 2012. (https://doi.org/10.1016/j.nucengdes.2012.04.021)
Chang H. OH, Eung S. Kim, Natural Circulation Patterns in the VHTR Air-ingress Accident and Related Issues, Nuclear Engineering Design, Vol. 249, pp. 228-236, 2012. (https://doi.org/10.1016/j.nucengdes.2011.09.031)
C O N T A C T
You may reach us via web form, or contact us by direct e-mail at
snueslab@gmail.com
snueslab@gmail.com
ADDRESS
Room 209, Building 31, Seoul National University
1, Gwanak-ro, Gwanak-gu, Seoul, Republic of Korea
TELEPHONE
+82-2-880-7216
개인정보 수집 및 이용동의 / 약관 보기
SEND