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.

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.

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. 

INNOVATIVE NUCLEAR SYSTEMS

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.

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.

ADDRESS

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

TELEPHONE

+82-2-880-7216