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
- Ancient Building
- 방금 전
- 1486
- 25
- 0
'태양의 도시' 바알벡, 레바논
마크 블레이즈
첫 번째 고대 건물은 레바논의 인상적인 바알벡 고고학 유적지입니다. 이 장엄한 장소는 아름다운 사원, 장엄한 돌 계단, 매력적인 안뜰 등이 있는 상당히 독특한 장소로 알려져 있습니다.
3
- Ancient Building
- 방금 전
- 1486
- 25
- 0
이탈리아 헤라의 고대 신전
마크 블레이즈
바로크 양식의 궁전과 대성당에서 장엄한 건물과 풍경에 이르기까지 이탈리아는 항상 우리가 가장 좋아하는 목적지였습니다. 이 고대의 사원은 이탈리아에 대한 또 다른 인상적인 특징입니다.
2
- Ancient Building
- 방금 전
- 1486
- 25
- 0
고대 그리스 파르테논 신전
잭 다니엘
그리스 아테네의 장엄한 신전은 또 다른 고대 건축물, 즉 그리스 파르테논 신전과 금과 상아 요소가 특징인 아름다운 아테나 동상으로 방문객들에게 깊은 인상을 남기고 있습니다.
1
- Ancient Building
- 방금 전
- 1486
- 25
- 0
고베클리 테페, 터키
데이비드 제임스
이 인상적인 사원은 최소 200개의 기둥과 다양한 동물이 조각된 수십 개의 암석으로 구성되어 있습니다. 이 덕분에 고대 괴베클리 테페는 세계에서 가장 높이 평가되는 건축물 중 하나가 되었습니다.
N E W P U B L I C A T I O N S
J A N 2 0 2 4 - P R E S E N T
- Ancient Building
- 방금 전
- 1486
- 25
- 0
'태양의 도시' 바알벡, 레바논
마크 블레이즈
첫 번째 고대 건물은 레바논의 인상적인 바알벡 고고학 유적지입니다. 이 장엄한 장소는 아름다운 사원, 장엄한 돌 계단, 매력적인 안뜰 등이 있는 상당히 독특한 장소로 알려져 있습니다.
3
- Ancient Building
- 방금 전
- 1486
- 25
- 0
이탈리아 헤라의 고대 신전
마크 블레이즈
바로크 양식의 궁전과 대성당에서 장엄한 건물과 풍경에 이르기까지 이탈리아는 항상 우리가 가장 좋아하는 목적지였습니다. 이 고대의 사원은 이탈리아에 대한 또 다른 인상적인 특징입니다.
2
- Ancient Building
- 방금 전
- 1486
- 25
- 0
고대 그리스 파르테논 신전
잭 다니엘
그리스 아테네의 장엄한 신전은 또 다른 고대 건축물, 즉 그리스 파르테논 신전과 금과 상아 요소가 특징인 아름다운 아테나 동상으로 방문객들에게 깊은 인상을 남기고 있습니다.
1
- Ancient Building
- 방금 전
- 1486
- 25
- 0
고베클리 테페, 터키
데이비드 제임스
이 인상적인 사원은 최소 200개의 기둥과 다양한 동물이 조각된 수십 개의 암석으로 구성되어 있습니다. 이 덕분에 고대 괴베클리 테페는 세계에서 가장 높이 평가되는 건축물 중 하나가 되었습니다.
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
Postdoctoral Researchers
Yelyn Ahn, Ph.D
Postdoctoral Researcher
zks1124@snu.ac.kr
#SPH, #Multi-GPU, #Parrallezation,
#HPC
Tae Hoon Lee, Ph.D
Postdoctoral Researcher
zrkanl0521@snu.ac.kr
#SPH, #Fluid Structure Interaction,
#IVR-ERVC
Jin Hyun Kim, Ph.D
Postdoctoral Researcher
uhaha118@snu.ac.kr
#SPH, #ASPH, # Shockwave, #Explosion,
#Structure Analysis
Ph.D Students
Hoon Chae
Hoon Chae
georgechae@snu.ac.kr
#SPH, #DEM, #MSR, #Raditive Heat
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
#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
Kyu Byung Lee
xxxx@snu.ac.kr
#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
Joong Young Seo
joongyeongseo@snu.ac.kr
#SPH, #DEM, #PBR, #Multiphysics
Ju Bin Kim
kimjubin1@snu.ac.kr
#FCI, #Steam Explosion,
#Severe Accident, #ML
Min Chan Kwon
ksn5014@snu.ac.kr
#FCI, #Corium Spreading,
#Severe Accident
MS Students
Sang Hoon Lim
jameslim@snu.ac.kr
#RHRS #GAMMA #MODELICA #MSR #DIGITAL TWIN
Min Jae Kim
minja2@snu.ac.kr
#MCCI #SPH
Jiho Kim
kjiho0403@snu.ac.kr
#Lattice Boltzmann Method
Su Hyun Kim
shy0519@snu.ac.kr
#ML #Source Term
Kyung Dong Lim
ikd2001@snu.ac.kr
#Velocity Field Reconstruction #ML
Sohyeon Ahn
ahn19@snu.ac.kr
#DEM #Ray Tracing #Radiative Heat
Hojin Jang
hojin9908@snu.ac.kr
#SPH #DEM #ML
Ji Hyun Lee
ss10248s@snu.ac.kr
#Dispersion, #Evacuation #Policy
Injae Kim
rladlswo678@snu.ac.kr
#Digitial Twin #MODELICA #Severe Accident
Hyun Heo
gjgus1997@snu.ac.kr
#SPH #DEM
Hong Sik Kim
kimhsboy@snu.ac.kr
#TBD
Ji Hee Lee
protein9603@snu.ac.kr
#TBD
Sang Jin Kim
xxxx@snu.ac.kr
#TBD
Undergraduate Students
Byeong Hyeon Ji
jihanjin2@snu.ac.kr
#TBD
Dong Ha Kim
guest0524@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
(HYU)
Assistant Professor
Young Beom Jo (Ph.D)
Kyung Hee University
(KHU)
Assistant 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 Cadrache, France)
Postdoctoral Researcher
Jin Hyun Kim (Ph.D)
Seoul National Univresity (SNU)
Postdoctoral Researcher
Yelyn Ahn (Ph.D)
Seoul National University (SNU)
Postdoctoral Researcher
Tae Hoon Lee (Ph.D)
Seoul National University (SNU)
Postdoctoral Researcher
R E S E A R C H E S
- MULTIPHYSICS
- EMERGENCY MANAGEMENT
- DIGITAL TWIN
Realistic Simulation Techonlogy based on Particle-based Methods
MULTIPHYSICS SIMULATION
for Nuclear System and Safety Innovations
"A well-constructed model is the scientist's most powerful tool to reveal hidden truths."
Developing a Multiphysics Simulation Framework
Utilizing Particle-Based Methods (PBMs) and High Performance Computing (HPC)
to Address Complex Problems in Nuclear Engineering
Smart and Reliable Emergency Response System based on Modern Computational Methods
EMERGENCY MANAGEMENT
for Nuclear Disasters
"Advanced modeling transforms emergencies into manageable challenges."
Developing a Smart and Reliable Emergy Response System
Integrating Artificial Intelligence (AI), High-Performance Computing(HPC), and Advanced Modeling Techniques
to Address Nuclear Ensuring Safety, Resilience, and Preparedness
Integrated Digital Twin Technology based on Open-source Object-oriented System Dynamic Analysis Platform
DIGITAL TWIN
for Advanced Nuclear Systems & Safety
"The digital twin is the key to unlocking a new dimension of innovation, bridging the gap between the virtual and physical worlds."
Developing an Integrated Digital Twin Platform for Advanced Nuclear Reactors,
Harnessing Cutting-Edge Computational Technologies, High-Performance Computing (HPC), and Advanced Modeling
to Enhance Safety, Optimize System Performance, and Drive Innovation in Nuclear Engineering
RECENT ACHIEVEMENTS
MULTIPHYSICS
Simulation of Shock Wave Propagation and Structural Interaction in Steam Explosion (Jin Hyun Kim)
This study developed a GPU-optimized Smoothed Particle Hydrodynamics (SPH) framework to simulate steam explosions in nuclear reactors, focusing on shockwave propagation and structural impacts. Simulations for the APR1400 reactor cavity showed that the equation of state (EOS) and structural materials significantly influence pressure and damage, with the Mie-Grüneisen EOS producing higher pressures and reinforced concrete offering greater resistance.
MULTIPHYSICS
Simulation of Reactor Vessel Impact on External Core Catcher (Jin Woo Kim)
This study demonstrated the SOPHIA platform's capability to simulate extreme nuclear accident scenarios, focusing on molten corium interactions with the reactor pressure vessel (RPV) and surrounding materials. The left image highlights the temperature distribution and material behavior during a gravitational drop of the RPV lower head, while the right images show deformation and plastic strain under extreme stress. These simulations provide critical insights into thermal-fluid and structural responses.
MULTIPHYSICS
Simulation of Corium Spreading on External Core Catcher (Hee Sang Yoo)
This study demonstrated the complex spreading behavior of molten corium with distinct physico-chemical properties at the ex-vessel core catcher during a severe nuclear accident. The simulation differentiates between oxide corium (high temperature, low viscosity, narrow mushy zone) and metal corium (lower temperature, high viscosity, wide mushy zone). The analysis provides critical insights into corium spreading dynamics for optimizing reactor safety systems and strategies.
MULTIPHYSICS
Simulation of Severe Accident Mitigation Strategy by In-Vessel-Retention through External Reactor Vessel Cooling (Yelyn Ahn)
This study demonstrated the use of multi-GPU parallelization with dynamic load balancing for large-scale simulations. It features 2-D domain decomposition and dynamic load balancing to optimize performance, utilizing 9 NVIDIA RTX 3090 GPUs and 9 NVIDIA RTX 4090 GPUs. The results demonstrate natural convection, Rayleigh-Bénard convection, and metal layer penetration patterns for IVR-ERVC simulation, with MPI facilitating GPU communication.
MULTIPHYSICS
Fluid-Structure Interaction Model based on SPH (Jin Woo Kim)
This study highlights the capability of SPH in tackling complex fluid-structure interactions, particularly those involving free-surface flows and large structural deformations. By eliminating the need for underlying meshes, SPH provides exceptional flexibility and adaptability, making it a valuable tool for simulating such challenging scenarios.
MULTIPHYSICS
Topology Optimization of Thermal Distributor for Heat Pipe Cooled Micro Reactor (Ju Hyeong Lee)
This study developed a generative design method for optimizing thermal distributors in heat pipe-cooled micro reactors (HPRs), particularly focusing on lightweight and efficient designs. Using multi-objective topology optimization with Smoothed Particle Hydrodynamics (SPH), the research enhances thermal resistance and structural stability while reducing material usage by 50%. The results demonstrate improved portability and sustainability of HPRs.
MULTIPHYSICS
Development of thermal analysis model using a GPU-based Ray Tracing (So Hyeon Ahn)
This study develops a GPU-based Monte Carlo Ray Tracing (MCRT) model for analyzing radiative heat transfer in pebble scale. The model accounts for local temperature variations on pebble surfaces and calculates view factors in complex geometries. By integrating conductive and radiative heat transfer, it provides accurate simulations of thermal conductivity, validated against experimental data. This approach enhances thermal analysis in high-temperature reactors.
MULTIPHYSICS
Simulation of Pebble Bed Reactor by Coupling SPH-DEM-NEUTRONICS Models (Joong Young Seo)
This study develops a new multiphysics scheme for analyzing the transient behavior of a PBR core. A mechanical/thermal particle scale analysis of pebble fuels were enabled by discrete element method(DEM), which is coupled with a SPH code to predict thermal behavior. Then, the SPH-DEM code exchanges local information with a neutronics code, which allows the accurate modeling of an operating PBR reactor. Based on these methodology, a simplified benchmark model of an operating HTR-10 reactor was modeled.
![[2024.12_.26]_연구실_홈페이지_업로드_.png](https://lh3.googleusercontent.com/co-TPnHX4TkVu1Lv42l-9BRmHBTN1w24yIzJSXxAnVDaDJHuJtYfjlIMYvD4Tmg1GIWQN0a-C9eU_ii6Ht-Bd9zh3zPRw0IfMrBR0S08tmt9kEwCfX2QcFI=w1920-h1080-n)
MULTIPHYSICS
Development of implicity steady SPH solver for helium bubbling simulation in molten salt reactor (Tae Hwan Kim)
This study is conducted to simulate helium bubbling phenomena in MSRs. While the SPH methodology is well-suited for multiphase and multiphysics analysis, it has the drawback of high computational cost. By developing an implicit steady solver, steady-state solutions can be computed efficiently and used as inputs for further analysis. Steady solver capable of implicitly calculating velocity, pressure, and temperature has been developed and validated.
HAZARD CONTROL
Simulation on Radioactive Dispersion in Nuclear Disaster and Public Evacuation (Joo Ryong Park)
This study visualized the dispersion of radioactive agents in an urban area and assesses its impact on the population. It analyzes the total dose exposure for agents over time, categorizing risks based on shelter effectiveness and agent distribution. Key insights include the variation in exposure levels, the progression of affected individuals over time, and the relative safety provided by different shelter locations. It analyzes the importance of strategic shelter placement and evacuation planning in mitigating radiation risks.
HAZARD CONTROL
Simulation on Radioactive Dispersion and Pathways in Urban Area (Joo Ryong Park)
This study visualized the dispersion of radioactive agents in an urban area and assesses its impact on the population. It analyzes the total dose exposure for agents over time, categorizing risks based on shelter effectiveness and agent distribution. Key insights include the variation in exposure levels, the progression of affected individuals over time, and the relative safety provided by different shelter locations. It analyzes the importance of strategic shelter placement and evacuation planning in mitigating radiation risks.
HAZARD CONTROL
Development of GPU Accelerated Level-3 PSA code (Joo Ryong Park)
This study developed a GPU-accelerated Level 3 PSA code utilizing 3D parallelization, achieving up to 1469x performance improvement compared to CPU-based implementations. Existing Level 3 PSA codes, such as MACCS and KAERI’s RCAP By leveraging GPU parallelization, this study effectively optimized the processing of weather data scenarios, evacuation models, and puff models, demonstrating the significant potential for performance acceleration in these applications.
HAZARD CONTROL
Wind field analysis in a realistic urban environment (Do Hyun Kim)
This study extends SOPHIA platform to an urban scale by incorporating realistic terrain and building data, leading to the development of an Urban SPH framework for city-scale wind field analysis. The figure below shows a wind field analysis using a portion of Seoul National University’s real building and terrain data. Through this study, we can gain detailed insights into complex urban turbulence, which can be applied to disaster preparedness, such as predicting the dispersion of radioactive materials.
HAZARD CONTROL
Development of LBM Solver for Urban Dispersion Simulation (Jiho Kim)
This study develops an advanced Lattice Boltzmann Method (LBM) framework for simulating urban dispersion. The presentation covers core LBM algorithms, enhancements for urban environments, and single-building simulation cases. Key improvements include Multiple Relaxation Time (MRT) and Large Eddy Simulation (LES) models to handle turbulence and convection. The study also highlights GPU-based parallel simulations and discusses code optimization and future expansion for real-world urban applications.
HAZARD CONTROL
Source Term Esitmation using GPU-based Ensemble Kalman Inversion (Siho Jang)
This study demonstrated the capability of Ensemble Kalman Inversion (EKI) for estimating multiple radionuclide source terms, offering significant advantages over traditional gradient-based methods. By utilizing a gradient-free approach, EKI circumvents the computational complexity and challenges inherent in gradient calculations. Furthermore, it enables inverse estimation while incorporating uncertainties, ensuring robust solutions even for ill-posed problems.
HAZARD CONTROL
Source Term Esitmation based on Neural Network (Su Hyun Kim)
This study proposes a novel methodology for source term estimation to support emergency response and reactor status analysis during severe nuclear accidents. From a Bayesian perspective, this study treats the inverse problem of source term estimation as a Bayesian update process. An AI-based methodology is introduced to determine the posterior probability distribution of source terms using the given gamma dose rate measurements. The results, based on a simplified dispersion model, demonstrate that the probability distribution evolves consistently with the sampling-based true distribution depending on the number and accuracy of measurement stations.
DIGITAL TWIN
Development of dynamic simulation model for 20 kWe micro heat pipe fission battery with dual power conversion system (Kyeong Jun Park)
This study designed and analyzed a dual power conversion system combining Thermoelectric Generators (TEGs) and Free-Piston Stirling Generators (FPSGs) for heat-pipe micro-reactors, addressing efficiency, stability, and reliability challenges in small-scale nuclear power generation. The complementary behaviors of TEGs and FPSGs ensure robust and reliable power generation for specialized applications.
DIGITAL TWIN
Development of Fuel Salt Freezing Model for System Analysis of Molten Salt Reactors (Sang Hoon Lim)
This study developed a solidification model for molten salt reactors (MSRs) to analyze potential freezing scenarios in emergency conditions, such as coolant loss or reactor shutdown. The model, implemented in the Modelica-based TRANSFORM library, simulates the solidification of fuel salt in systems like emergency drain pipes and passive cooling loops, highlighting the risks of flow blockages and reduced heat removal.
MISCELLANEOUS
Feasibility Analysis of Cryptocurrency Mining Using Nuclear Surplus Electricity (Jihyun Lee)
This study develops the legal and economic feasibility of using surplus electricity generated by nuclear power plants for cryptocurrency mining. By utilizing surplus energy, traditionally discarded or underused, this model aims to create economic value while promoting energy efficiency. The research includes an analysis of the potential profitability through Benefit-Cost ratio (BCR) and highlights specific case studies of nuclear power plants (Wolsung #3 and Shin-Kori #2).
SIMULATION GALLERY
P U B L I C A T I O N S
Park, Kyeong Jun et al., "Development of dynamic simulation model for 20 kWe micro heat pipe fission battery with dual power conversion system." Applied Thermal Engineering 258 (2025): 124505. (https://doi.org/10.1016/j.applthermaleng.2024.124505)
Kim, JinHyun, et al. "Simulation of shockwave propagation characteristics in nuclear reactor cavity during external steam explosion using unified SPH." Nuclear Engineering and Technology (2024). (https://doi.org/10.1016/j.net.2024.10.036)
Yoo, Hee Sang, and Eung Soo Kim. "Numerical investigation of spreading phenomena of molten corium using EISPH method." Nuclear Engineering and Technology (2024). (https://doi.org/10.1016/j.net.2024.11.003)
Ahn, Yelyn, et al. "Dynamic Load Balancing of Multi-GPU Parallelization for VULCANO VE-U7 Corium Spreading Analysis Using SOPHIA." Nuclear Technology (2024): 1-21. (https://doi.org/10.1080/00295450.2024.2397617)
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)
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 ~
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- 2022. 3 ~
- 고효율 저탄소 원자력-가스 복합 시스템 기술 개발
- 2022. 1 ~
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- 2022. 1 ~
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- 2021. 3 ~
- 입자형 노심 기반의 마이크로 원자로 배터리 기술 개발
- 2021. 9 ~
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