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High Performance Computing Group
for Nuclear Systems and Safety


Innovation of Nuclear Systems & Safety through Advanced Modeling & High Performance Computing

High Performance Computing Group
for Nuclear Systems and Safety


Innovation of Nuclear Systems & Safety through Advanced Modeling & High Performance Computing

High Performance Computing Group
for Nuclear Systems and Safety


Innovation of Nuclear Systems & Safety through Advanced Modeling & High Performance Computing

High Performance Computing Group
for Nuclear Systems and Safety


Innovation of Nuclear Systems & Safety through Advanced Modeling & High Performance Computing

High Performance Computing Group
for Nuclear Systems and Safety


Innovation of Nuclear Systems & Safety through Advanced Modeling & High Performance Computing

About

Our laboratory is addressing technical challenges in nuclear systems & safety using advanced modeling, high-fidelity experiment, and innovative design empowered by high performance computing.

Prof. Eung Soo Kim, Head of High Performance Computing Group for Nuclear Systems & Safety 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
​News (2022. 5. 17)

SPH 2-D Dynamic Load Balancing for SOPHIA Multi-GPU Framework



2-D dynamic load balancing has been sucessfully establihsed for SOPHIA Multi-GPU Framework. Ms. Yelyn Ahn made a big effort on this work. Now, SOPHIA code can handle unlimitted number of GPUs in MPI framework and performance can be effectively optimzed using the new platform. Big progess!  Performance benchmark will be conducted soon.
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 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)

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. 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!
News (2021. 9. 15)

Fission Battery "Our First Design of Heat Pipe Micro Reactor"


The GMR research group including Dr. Young Beom Jo, Su-san Park, Jin Hyun Kim, Chae Hoon, Jin Woo Kim, Jong Sung Chi created our first design of nuclear fission battery based on heat pipe micro-reactor concept. This 10 kWe reactor integrated a solid core, heat pipes, and a thermoelectric generator. This concept will be a great corner stone for our new innovative concepts under development.  

New Simulations (2021. 12. 3)

Adaptation of Modeling Capability for HTGR Accidents Analysis in SOPHIA


Tae Soo Choi, Jin-Woo Kim, and Do-Hyun Kim recently adopted models for the high temperature gas-cooled reactor (HTGR) accident analysis into the SOPHIA code! Full multi-component gas mixture, gas EOS, molecular diffusion, chemical reactions with various new numerical schemes have been implemented! Big progress in the SOPHIA code framework! This simulation was conducted under the I-NERI project collaborated between Seoul National University (ROK) & University of Michigan (US).
(http://www.youtube.com/embed/1y9f2h9Bq3c?wmode=transparent)

News (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.

Award (2021. 10. 20)

Do-hyun Kim "KNS 2021 Best Paper Award"


Do-hyun Kim is awarded the Best Paper Award in KNS 2021 Spring Meeting for his paper entitled as "Implementation of GPU-based Adaptive Particle Refinement Numerical Scheme for Smoothed Particle Hydrodynamics :Preliminary Test for FCI Jet Breakup Simulation".  Congratulations!

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/).   

‌

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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
BK Postdoctoal Researcher
paul406@snu.ac.kr
#SPH, #DEM. #Multi-phase,
#Severe Accident, #Granular Micro Reactor
Il-Woong Park, Ph.D
Research Professor
ilwoongpark@gmail.com
#Multi-phase, #Phase-change, #Heat Transfer
#Experiment, #Energy Harvesting



Ph.D Students

Tae Soo Choi
bbada3290@snu.ac.kr
#SPH, #Gas, #Turbulence
Soo San Park
michle11@snu.ac.kr
#SPH, #MHD, #Pinch Plasma, #Granular Micro Reactor
Jin Hyun Kim
uhaha118@snu.ac.kr
#SPH, #ASPH, 
#Shockwave, #Explosion, #Granular Micro Reactor
Yelyn Ahn
zks1124@snu.ac.kr
#SPH, #Bubble Dynamics, 
#Phase-Field-Model, #HPC, #GPU
Hee Sang Yoo
yhs0365@snu.ac.kr
#SPH, #Surface Tension, #Microfluidics, #ALE, #Axisymmetric
Tae Hoon Lee
zrkanl0521@snu.ac.kr
#SPH, #Structure, #FSI, #GIS, #Evacuation, #ABM
Hoon Chae
georgechae@snu.ac.kr
#SPH, #DEM, #Boiling, 
#Non-spherical, #Granular Micro Reactor
Jin Woo Kim
wlsdn1362@snu.ac.kr
#SPH, #Gas, #Reaction,
#Boundary Condition, #Granular Micro Reactor
Jun Sung Choi
‌cjs8088@snu.ac.kr
#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
Tae Hwan Kim
hwan0703@snu.ac.kr 
#SPH, #Axi-symmetric, #MCCI
Siho Jang
siho.jang86@gmail.com
#Dispersion, #Back-trajectory, # Source-Receptor Model
Kyu Byung Lee
xxxx@snu.ac.kr
#Severe Accident, #Nuclear Safety



MS Students

Jongsung Chi
chijongsung@snu.ac.kr
#Micro-Reactor, #Nuclear Underwater Vehicle
Da Kyung Lee
xxxx@snu.ac.kr
#Energy Harvesting #Nuclear Safety
Kyung Jun Park
815rudwns@gmail.com
#Micro-reactor #Marine Propulsion



Undergraduate Students

Jihyun Lee
 ss10248s@snu.ac.kr
#Dispersion, #Evacuation‌
Hyun Heo
 gjgus1997@snu.ac.kr
#SPH, #DEM, #Bonding Model, #Non-spherical DEM‌
Joong Yeong Seo
 joongyeongseo@snu.ac.kr
#SPH, #DEM, #Pebble Bed Reactor‌
Ju Bin Kim
 geniuskimjb@naver.com
#SPH, #GPU, #Texture Memory‌
Jiho Kim
 kjiho0403@snu.ac.kr
#Lattice Boltzmann Method‌
Min Chan Kwon
ksn5014@snu.ac.kr
#​TBD‌
Sang Hoon Lim
jameslim@snu.ac.kr
#TBD‌
Chan Woo Jung
 todrkfcl2040@naver.com
#​TBD‌



Administrator

Eui Nae Cho

 shan77@snu.ac.kr
#Adminitration‌



Alumni

Min Young Park (Ph.D)

Korea Atomic Energy Research Institute (KAERI)
Senior Researcher

Min Seop Song (Ph.D)

Idaho National Laboratory,  USA
(INL)
Staff Researcher

Young Beom Jo (Ph.D)

Seoul National University
(SNU)
BK Postdoc

Jae Soon Kim (Ph.D)

Korea Institute of Nuclear Safety
(KINS)
Senior Researcher

Serin Shin (M.S)

Korea Atomic Energy Research Institute (KAERI)
Researcher

Ji Hyun Seong (M.S)

Los Alamos National Laboratory, USA
(LANL)
Postdocoral Researcher

Dokyun Lim (M.S)

Korea Institute of Nuclear Safety, Korea
(KINS)
Staff Researcher

So-Hyun Park (Ph.D)

Korea Atomic Energy Research Institute
(KAERI)
Senior Researcher

Hae Yoon Choi (Ph.D)

SAMSUNG Electronics
(SAMSUNG)
Researcher






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

IVR-ERVC Simulation using SPH and 1-D System Code
Multi-Jet Mixing Simulation using SPH
Self-leveling Simulation using SPH-DEM Copuling
X-Pinch Plasma Simulation using SPH
Fuel Coolant Interaction Simulation using SPH
Shockwave and Structure Simulation using SPH
Electrolytic Reduction Simulation using SPH
Micro-fluidic Simulation using SPH
S I M U A L T I O N   G A L L E R Y - 2

Euler-Lagrangian ISPH Scheme for Natural Convection
EISPH Simulation for Multi-phase Flow
Euler-Lagrangian Scheme for Free Surface Flow
Granular Particle Falling Simulation using DEM
Brazilian Nuts Simulation using DEM
3-Field Coupling Simulation using SPH and DEM
Double-Diffusive Convection Simulation using SPH
Fliud Structure Interaction Simulation using SPH
Fliud-Rigid Body SImulation using SPH
S I M U A L T I O N   G A L L E R Y - 3

Dispersion Simulation with Evacuation
Disersion Simulation using LDM
Coupling of LDM and CFD

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





Choi, H. Y., Chae, H., and Kim, E.S.*, Numerical Simulation on Jet Breakup in the Fuel-Coolant Interaction Using Smoothed Particle Hydrodynamics, Nuclear Engineering and Technology, 2020 (under review).

Yoo, H. S., and Kim, E.S.*, Numerical Analysis on Water Entry of Spherical Projectiles with Various Wettability using Smoothed Particle Hydrodynamics, Ocean Engineering, 2020 (under review).

Park, S.S., Kim, J.H., Park, S.H., and Kim, E.S., SPH Simulation for Pinch Plasma using Non-ideal Resistive MHD Model, TBD, 2020 (in preparation).


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).


Jo, Y.B., Park, S.H., Kim, E.S., Simulation of Vapor Induced 3-Phase Sloshing Behavior using Multi-phase SPH-DEM Coupling, TBD, 2020 (in preparation).


Park, S.H., Chae, H., Jo, Y.B., Kim, E.S.*, Weakly Compressible Smoothed Particle Hydrodynamics for General Gradient Driven Flow, TBD, 2020 (in preparation).


Song, M.S., Jeong, J.H., Kim, E.S.*, CFD Analysis on 19-pin and 32-pin KAERI SFR Wire-wrapped Fuel Bundle Hydraulic Experiments, Nuclear Engineering and Design, 2020 (Accepted‌).


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.

Contact

You may reach us via web form, or contact us by direct e-mail at
snueslab@gmail.com

ADDRESS

Room 209, Building 31, Seoul National University
1, Gwanak-ro, Gwanak-gu, Seoul, Republic of Korea

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