IMMAGINATION
Versatile Computational Solutions
for Nuclear Systems and Safety
- REALITY
About Us
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.
Prof. Eung Soo Kim, a Lead of Nuclear Energy System Laboratory at Seoul National University
Introduction to ESLAB
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 U N E 2 0 2 1 - P R E S E N T
New Publication (2023. 2. 28)
Lagrangian Computational Fluid Dynamics for Nuclear Thermal-Hydraulics and Safety - by Young Beom Jo
A review paper on Lagrangain computational fluid dynamics for nuclear thermal-hydraulics and safety has been published in Nuclear Engineering and Design (NED) recently. This paper has been published in the special issue following the OECD-NEA specialist meeting in 2022. Dr. Young Beom Jo made a big effort on this publication. (https://doi.org/10.1016/j.nucengdes.2023.112228)
New Publication (2023. 2. 28)
Modelling and analysis of salt-convection effect on oxide reduction process for uranium oxides - by Jin Woo Kim
A new paper has been published in the International Journal of Heat and Mass Transfer (IJHMT). In this paper, a multiphysics kinetic model of oxide reduction process for uranium oxides was presented coupled with active salt convection, based on smoothed particle hydrodynamics. Mr. Jin Woo Kim made a big effort on this publication. (https://doi.org/10.1016/j.ijheatmasstransfer.2023.123965)
New Publication (2023. 2. 28)
Deep Learning-based Spatial Refinement Method for Robust High Resolution PIV Analysis - by Jun Sung Choi
A new paper has been published in the Experiments in Fluid (EIF). In this paper, a PIV velocity refinement method based machine learning algorithm has been developed and sucessfully applied to the measured image pairs. Mr. Jun Sung Choi made a big effort on this publication. (https://doi.org/10.1007/s00348-023-03595-x)
Event (2022. 12. 16)
Celerbration of ESLAB 10th Anniversary
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.
New Achivements (2023. 1. 17)
Dynamic Simulation Model for Heat Pipe Nuclear Fission Battery System - by Jong Sung Chi
A dynamic simulation model for 10 kWe nuclear fission battery based on heat pipe cooling. This model incoorperated a core, heat pipe, and thermoelectric generator. Neutronics feedback effect was considered using point kinetics. Various simulations have been conducted for postulated transient scenarios. Mr. Jong Sung Chi made a big effort on this task! This work was presneted in IZES conference at Tokyo.
New Publication (2023. 1. 17)
Selected Featured Cover for Int. Journal of Numerical Method in Engineering
A new paper has been published and selected as a Featured Cover in International Journal for Numerical Methods in Engineering. In this research, a simple robust method for Eulerian-Langrangian SPH simulation has been proposed and validated for various test simulations. Mr. Hee Sang Yoo conducted this research mainly and made tremendous effort to obtain good results. Dr. Young Beom Jo, Mr. Jin Woo Kim, and Mr. Tae Soo Choi also contributed this research. Great achievements! (https://doi.org/10.1002/nme.7148)
New Simulation (2022. 12. 23)
GPU Implemenation on DEM Nonspherical Model - by Hyun Heo
A DEM non-spherical particle model has been newly implemented into the SOPHIA code in the GPU framework. Several GPU parallel algorithms were implemented and tested for optimization of the calculation performance. Mr. Hyun Heo and Dr. Young Beom Jo made a big effort on this task. Great work! More details can be seen in the following link: (https://youtu.be/KsTYdvE3KFk)
New Simulation (2022. 12. 15)
Realistic X-Pinch Simulation using SPH - by Su San Park
A realistic X-Pinch simulation has been conducted using smoothed particle hydrodynamics (SPH). This new model incoorperated plasma hydrodynamics and radiation effects. Various radiation models have been implemented and compared together. This is the first full-scope X-Pinch simulation and sucesfully captured key phenomena observed in the experiments. Mr. Su-San Park conducted this research and made tremendous job to achieve it! The details can be seen in the following link: (https://youtu.be/bvi48HEDLC8)
News (2022. 10. 28)
Keynote Lecture at NTHAS-12 Student Session - by Dr. Young Beom Jo
Our lab attended NTHAS-12 conference held in Miyazaki, Japan. In this conference, a joint student program was held together to exchange knowlege and friendship between Korea and Japan for nuclear thermal-hydraulics & safety. Dr. Jo was invited to talk as a keynote lecturer in this prgram. He presented and shared his vision about meshless numerical methods and high performance computing (HPC) for nuclear engineering.
News (2022. 11. 14)
Coupling of SOPHIA with OpenFOAM using PreCICE
The SOPHIA code has been sucessfully coupled with OpenFOAM. To conduct this work, a PreCICE adapter for the SOPHIA code has been newly developed by Mr. Do-Hyun Kim. This work is the first step to couple the SOPHIA code with other external codes based on various numerical methods such as FVM, FEM, FDM, and etc. Lots of potential researches are expected following this work.
News (2022. 11. 14)
Adapting Dynamic Load Balancing Capability for Multi-GPU SPH
Dynamic load balancing with adaptive domain decomposition has been recently acheived for Multi-GPU SPH simultion. The SOPHIA code has been fully parallelized using Message Passing Interface (MPI) and optimized. As a result, the computational loads for the GPUs are perfectly balanced during the simulation. This outstanding work has been performed by Ms. Yelyn Ahn.
News (2022. 8. 29)
Dynamic LES Model Implementation for SPH Simulation
In the present study, the subgrid-scale (SGS) eddy-viscosity model developed by Vreman and its dynamic version have been implemented and tested in Smoothed Particle Hydrodynamics (SPH) framework. In Vreman model, subgrid-scale dissipation for laminar shear flows is vanished theoretically with non-zero constant empirical model coefficient. Transient behaviors of turbulent structures are well captured compared with the standard Smargoninsky model in SPH. Tae Soo Choi made a big contribution to this great work.
New Simulation (2022. 8. 25)
Lagrangian Dispersion Simulation Coupled With Computational Fluid Dynamics
Lagrangian Diseprsion Simulation (LDS) has been conducted by coupling with computational fluid dynamics. The LDS was fully parallelized using multi-GPUs and the CFD simulation was conducted using ANSYS CFX. The trajectories of the released partices have been well captured by this simulation framework. LDM-CFD coupling model has been validated by comparisons with benchmark simulations. Ju-Ryoung Park made a significant contribution to this outstanding work.
News (2022. 5. 17)
Lagrangian Dispersion Model Coupled with Computational Fluid Dynamics
Lagrangian Dispersion Model (LDM) has been well coupled with computational fluid dynamic (CFD) for simulation of particle dispersion. ANSYS-CFX code generated velocity field based on RANS-based turbulence models. Turbulence parameterization for the LDM model has been conducted using the turbulence parameters from CFD. Ju-Ryoung Park made a significant contribution to this nice work. In this simultion, the LDM model was fully parallelized using a GPU.
News (2022. 5. 27)
Our Recent Research Activities Introduced in International Journal of Multiphase Flow
Our recent activities on SPH & DEM research have been publisehd in International Journal of Multiphase Flow led by Dr. Young Beom Jo. a three-phase flow solver was established in this study by coupling the DEM with a Lagrangian smoothed particle hydrodynamics (SPH) model while adopting the unresolved phase coupling between the two techniques. In order to overcome the low computational efficiency of these two numerical methods, (https://www.sciencedirect.com/science/article/pii/S0301932222001239?dgcid=author).
New Publication (2022. 3. 8)
Editor's Pick in AIP Advances - SPH Wettability Simulation by Hee Sang Yoo
Our new paper entitled as "Effect of wettability on the water entry of spherical projectiles: Numerical analysis using smoothed particle hydrodynamics" has been recently publised in AIP advances. Hee Sang Yoo main-authored this paper and Hae Yoon Choi, and Tae Hwan Kim contributed it as well. This paper is also selected as an Editor's Pick in the latest issue and introduced in the journal main page. Conguratulations and great job! (https://aip.scitation.org/doi/10.1063/5.0072710)
News (2022. 3. 8)
Our Recent Research Activities Introduced in SPHERIC-Newsletter
Our recent activities on SPH code development and applications to nuclear severe accidents are introducted in the latest issue on SPHERIC-Newsletter. SPHERIC is the world leading research community in SPH method. Dr. Young-Beom Jo main-authored this article and Hee Sang Yoo, Tae Soo Choi, Tae Hoon Lee, Jin Woo Kim contributed it as well. Thank you for your large effort and well deserved. (https://www.spheric-sph.org/newsletters).
New Progress (2021. 2. 28)
Deep Learning Algorithm for High Resolution Resolution PIV Mearsurement
Joon Sung Choi developed a novel deep learning algorithm for enhancing spatial resolution of particle-image-velocimetry (PIV) measurement. In this method, the deep learning algorithm based on FLOW-NET2 was applied to the conventional cross-correlation based PIV. According to his recent benchmark analysis, the new method was found to provide outstanding performance even compared to the state-of-the-art methods. This research was collaborated with Dr. Ji Hyun Seong at Los Alamos National Laboratory (LANL) in USA and is in preparation for submission to a SCI Journal. Big progress!
New Progress (2022. 2. 28)
SPH Modeling for Oxide Reduction Process in Pyro-Processing
In the pyro-processing, oxide reduction process which converts uranium oxides to metals is essential to feed the metallic product in subsequent processes. To model its reduction kinetics, the phase interface between molten salt and oxide materials should be located effectively. Armed with the interface tracking capability, the SPH simulation reproduced the experimental observations successfully and estimated effects of basket thickness, feed material shapes and molten salt flow on the reduction process in complex and realistic reduction geometries. Jin Woo Kim conducted this modeling by collaboration with Idaho National Laboratory (INL) researchers.
New Progress (2021. 7. 1)
SOPHIA Code "Acquired Multi-Node Multi-GPU Parallel Computing Capability"
The SOPHIA code, a particle-based multi-physics simulation code based on GPUs, recently acquired multi-node, multi-GPU computing capability led by Yelyn Ahn and Dr. Nam Jae Choi. The SOPHIA code now can handle unlimited number of CPUs and GPUs for large scale particle-based simulation. Dr. Young-Beom Jo and Ju-Ryong Park also supported this great achievement.
News (2020. 10. 30)
SOPHIA Code "License Agreement with OECD-NEA Databank"
The SOPHIA code, a particle-based multi-physics simulation code based on GPUs, finally made license agreement with OECD-NEA Databank. The SOPHIA code is now officially released to the OECD-NEA Member Countries and USA & Canada. Refer to the following link (https://www.oecd-nea.org/tools/abstract/detail/nea-1911/).
Members
Professor
Prof. Eung Soo Kim
· 2021 ~ Professor, Seoul National University, South Korea
· 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
Research Scholars
Young Beom Jo, Ph.D
Research Professor
paul406@snu.ac.kr
#SPH, #DEM. #Multi-phase,
#Severe Accident, #Granular Micro Reactor
Postdoctoral Researchers
Tae Soo Choi, Ph.D
Postdoctoral Researcher
bbada3290@snu.ac.kr
#SPH #Turblence
Soo San Park, Ph.D
Postdoctoral Researcher
michle11@snu.ac.kr
#SPH #MHD #Pinch Plasma
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
Hee Sang Yoo
yhs0365@snu.ac.kr
#SPH, #Surface Tension, #Microfluidics, #ALE, #Axisymmetric
#SPH, #Surface Tension, #Microfluidics, #ALE, #Axisymmetric
Tae Hoon Lee
zrkanl0521@snu.ac.kr
#SPH, #Structure, #FSI, #GIS, #Evacuation, #ABM
#SPH, #Structure, #FSI, #GIS, #Evacuation, #ABM
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, #Gas, #Reaction,
#Boundary Condition, #Granular Micro Reactor
#SPH, #Gas, #Reaction,
#Boundary Condition, #Granular Micro Reactor
Jun Sung Choi
cjs8088@snu.ac.kr
#Flow Visualization, #Machine Learning,
#PIV, #MCCI
#Flow Visualization, #Machine Learning,
#PIV, #MCCI
Ju Ryong 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
MS Students
Da Kyung Lee
dkyoun.g@snu.ac.kr
#Energy Harvesting #Nuclear Safety
Kyung Jun Park
815rudwns@gmail.com
#Micro-reactor #Marine Propulsion
#Micro-reactor #Marine Propulsion
Hyun Heo
gigus1997@snu.ac.kr
#SPH #DEM #MSR #RHRS
Joong Yeong Seo
joongyeongseo@snu.ac.kr
#SPH #DEM #PBR
Sang Hoon Lim
jameslim@snu.ac.kr
#RHRS #GAMMA
Min Jae Kim
xxxx@snu.ac.kr
#MCCI #Severe Accident
Ju Bin Kim
xxxx@snu.ac.kr
#FCI #Severe Accident
Min Chan Kwon
ksn5014@snu.ac.kr
#FCI #Severe Accident
Undergraduate Students
Jihyun Lee
ss10248s@snu.ac.kr
#Dispersion, #Evacuation
#Dispersion, #Evacuation
Jiho Kim
kjiho0403@snu.ac.kr
#Lattice Boltzmann Method
Kyung Dong Lim
ikd2001@snu.ac.kr
#TBD
Su Hyun Kim
kshy0519@snu.ac.kr
#TBD
Administrator
Eui Nae Cho
shan77@snu.ac.kr
#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
(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)
Researcher
Il Woong Park (Research Prof.)
Inha University
(Mechnanical Engineering Dept.)
Assistant Professor
Jongsung Chi (M.S.)
Republic of Korea Navy
(ROKN)
Lieutenant Commander
Researches
PARTICLE-BASED SIMULATION
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.
S I M U L A T I O N G A L L E R Y - 1
S I M U A L T I O N G A L L E R Y - 2
S I M U A L T I O N G A L L E R Y - 3
Coupling of LDM and CFD
CFD-LDM Coupling Simulation
Dispersion Simulation with Evacuation
Disersion Simulation using LDM
FLOW VISUALIZATION
In recent years, the high-fidelity experimentation became a critical tool for verification & validation of advanced computational methods in nuclear systems and safety. Flow visualization is an experimental technique that visualizes flow fields & structures, which enables to analyzes their characteristics. We use laser-based flow visualization techniques such as PIV, PLIF, etc with advancing the state-of-the-art measurement techniques.
Refractive Index Matching with Planar Laser Induced Fluorescence for Particle Image Velocimetry
Refractive Index Matching of 3-D Printing Model Using Synthetic Working Fluid
MICRO NUCLEAR REACTOR SYSTEM
In addition to nuclear safety, our lab is conducting research for innovative nuclear system development. One of the key factors about the Fourth Industrial Revolution is how to supply the energy needed. To this end, we are developing a micro-battery system based on fission power. The basic concept of this system is an integration of Triso fuel, granular core, heat pipe, and thermoelectric generator, with no coolant, no mechanical parts, and simple principles.
Fission Battery System for Autonomous Unmanned Underwater Vehicle.
Screenshot of design software of Heat-pipe Micro-Reactor Battery System for Autonomous Unmanned Underwater Vehicle.
Projects
G O V E R N M E N T
- 2022-2024
- 선원항 평가를 위한 역추적모델 개발 (한국원자력안전기술원) [주관]
- 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]
- 2022-2024
- Viscoplastic 거동을 고려한 IVR-ERVC 조건 하 원자로 압력용기의 변형 및 파손 예측 모델 개발 (한국원자력안전재단) [참여]
- 2019-2021
- 완화입자유체동역학 기반의 노심용융물 노내거동 전산해석 방법 개발 (한국원자력안전재단) [주관]
- 2019-2022
- SPH 기반의 액적-표면 상호작용모의 전산해석 기법 개발 (한국연구재단) [주관]
- 2019-2021
- 고해상도 HTGR 실험데이터를 활용한 라그랑지안 기반의 원자력 안전 및 열유동 해석 원천기술 개발 및 검증 (한국연구재단) [주관]
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
Publications
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),
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).
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).
Kim, Jin-Woo, et al. "Smoothed particle hydrodynamics modeling and analysis of oxide reduction process for uranium oxides." Chemical Engineering Science 261 (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.
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.
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.
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.
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.
An, Y.R., Jo, Y.B., Park, S.H., Kim, J.W., Kim, E.S.*, Modeling Bubble Lifting Behavior in Linear Shear Flow using Smoothed Particle Hydrodynamics, International Journal of Multi-phase Flow, 2020 (in preparation).
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.
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.S., Kim, E.S.*, Jamming probability of granular flow in 3D hopper for non-Janssen saturation regime: DEM analysis, Granular Matter, Vol. 77, 2020. (10.1007/s10035-020-01050-w)
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
Chang H. Oh, Eung S. Kim, Conceptual Study on Air Ingress Mitigation for VHTRs, Nuclear Engineering & Deisgn, Vol. 250, pp. 448-464, 2012.
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.
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.S., Kim, E.S.*, Jamming probability of granular flow in 3D hopper for non-Janssen saturation regime: DEM analysis, Granular Matter, Vol. 77, 2020. (10.1007/s10035-020-01050-w)
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
Chang H. Oh, Eung S. Kim, Conceptual Study on Air Ingress Mitigation for VHTRs, Nuclear Engineering & Deisgn, Vol. 250, pp. 448-464, 2012.
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.
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