SITE IN PROGRESS · 연구실 홈페이지를 준비하고 있습니다.

MONAMI LAB

Multiphysics fOr Nuclear Analysis, Modeling and Innovation · Jeonbuk National University

원자력 다물리 해석·모델링 연구실 · Since 2026

차세대 원자력 시스템을 위한 계산과학.

입자 기반 고정밀 해석부터 원자로 계통 모델링까지, 물리와 계산을 연결하여 복잡한 원자력 시스템을 연구합니다.

연구 분야 보기 MONAMI 지원하기

연구 소개

MONAMI 연구실에서는 차세대 원자력 시스템의 해석을 위한 계산과학 및 시뮬레이션 기술을 연구합니다.

복잡한 유동과 다물리 현상을 정밀하고 효율적으로 해석하기 위한 입자 기반 수치해석 기법과 GPU 병렬계산 기술을 개발하는 한편, 원자력 열수력을 중심으로 계통 수준의 모델링과 상세 고정밀 수치해석을 연계하는 다중스케일 연구도 수행합니다.

이러한 계산 기술을 바탕으로 차세대 원자로의 정상 운전, 과도 상태 및 중대사고에서 나타나는 다양한 현상을 예측하고 안전성을 평가하고자 합니다. 장기적으로는 다물리·다중스케일 해석으로 연구 범위를 확장하고, 물리 기반 시뮬레이션과 데이터를 결합한 원자력 디지털트윈의 계산 기반을 구축하는 것을 목표로 합니다.

MONAMI Lab studies computational science and simulation technologies for the analysis of advanced nuclear systems. With a focus on nuclear thermal hydraulics, we connect system-level modeling with detailed high-fidelity numerical analysis and develop particle-based methods and GPU-parallel computing technologies for complex flow and multiphysics phenomena.

These capabilities support the prediction and safety assessment of advanced reactors under normal operation, transients, and severe accidents. In the long term, we aim to extend our work toward multiphysics and multiscale analysis involving reactor physics and structural mechanics, establishing a computational foundation for nuclear digital twins that combine physics-based simulation with data.

Visual overview of MONAMI Lab research from reactor system modeling through multiphysics simulation to digital twins

Research vision

Connecting physics, computation, and prediction.

We build reliable computational pathways from physical models to high-fidelity simulation, integrated analysis, and nuclear digital twins.

01

Physical Modeling

Represent the governing physics of reactor systems and their components.

02

High-Fidelity Computing

Resolve complex local phenomena using particle methods and GPU parallelization.

03

Multiphysics Integration

Connect solvers, physical scales, and feedback across reactor behavior.

04

Digital Twin

Combine physics-based simulation and data for fast, predictive analysis.

Each level informs the next—and improved predictions feed back into better physical models.

물리 모델에서 예측 기술까지 연결합니다.

물리 모델링, 고정밀 계산, 다물리 통합 해석을 연결하여 원자력 디지털트윈으로 확장할 수 있는 신뢰도 높은 계산 체계를 구축합니다.

01

물리 모델링

원자로 계통과 구성요소를 지배하는 물리 현상을 모델링합니다.

02

고정밀 계산

입자 기반 수치기법과 GPU 병렬계산으로 복잡한 국소 현상을 해석합니다.

03

다물리 통합

해석기와 물리 규모를 연결하여 원자로의 상호작용과 피드백을 분석합니다.

04

디지털트윈

물리 기반 시뮬레이션과 데이터를 결합하여 빠르고 신뢰도 높은 예측을 지향합니다.

각 단계의 결과는 다음 단계로 이어지며, 향상된 예측은 다시 물리 모델의 개선으로 연결됩니다.

Latest updates

News

MONAMI Lab launches at Jeonbuk National University.

MONAMI Lab begins its research in high-fidelity multiphysics simulation, reactor digital twins, and HPC-based particle methods.

Research directions

Computational science for predictive nuclear systems.

Our research connects nuclear multiphysics, high-fidelity computation, advanced reactor analysis, and data-informed modeling across scales.

SITE IN PROGRESS · 준비 중
01 · MULTIPHYSICS

Nuclear Multiphysics Simulation

Integrating reactor physics, thermal hydraulics, and structural mechanics through coupled models and simulation codes for steady-state and transient reactor analysis.

ACTIVE · 연구 진행 중
02 · HIGH-FIDELITY ANALYSIS

High-Fidelity Computational Analysis

Resolving complex local phenomena—including multiphase flow, free surfaces, melting and solidification, and severe accidents—using particle methods and GPU computing.

Go to page → ACTIVE · 연구 진행 중
03 · ADVANCED REACTORS

Advanced Reactor Modeling & Simulation

Exploring diverse Generation IV reactor concepts, with current emphasis on core and system modeling and transient analysis for molten salt reactors (MSRs).

Go to page →
SITE IN PROGRESS · 준비 중
04 · DIGITAL TWIN & AI

Physics-Based Digital Twin & AI

Combining physics-based simulation with experimental and operational data through reduced-order models, surrogate models, AI, and state estimation for fast reactor prediction.

MONAMI Lab

People

Portrait of Hee Sang Yoo

Principal Investigator

Hee Sang Yoo, Ph.D.

Assistant Professor, Department of Quantum Systems Engineering

Jeonbuk National University

heesang.yoo@jbnu.ac.kr

+82-63-270-4993

Google Scholar LinkedIn

Career

  • Assistant ProfessorJeonbuk National University
  • Postdoctoral ResearcherCEA Cadarache, FranceSupervisor: Dr. Claire Vaglio-Gaudard
  • Postdoctoral ResearcherSeoul National UniversitySupervisor: Prof. Eung Soo Kim

Education

  • Ph.D. in Nuclear EngineeringSeoul National UniversitySupervisor: Prof. Eung Soo Kim
  • B.E. in Nuclear EngineeringSeoul National University

Awards

  • Best Paper AwardAmerican Nuclear Society (ANS), 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21)
  • Best Paper Award Main AuthorKorean Nuclear Society (KNS) Spring Meeting
  • Best Paper AwardKorean Nuclear Society (KNS) Autumn Meeting
  • Best Poster Award Main AuthorKorean Nuclear Society (KNS) Autumn Meeting

Publications

Research Publications

Journal articles, conference presentations, and scientific software that establish the computational foundations of MONAMI Lab.

Selected recent papers - click a first page to enlarge

First page of the Renewable and Sustainable Energy Reviews paper
J16 - 2026

From Water to Dielectric Fluids

This review clarifies how pressure and subcooling govern boiling performance in dielectric fluids for next-generation cooling systems.

DOI ↗
First page of the Computational Mechanics paper
J12 - 2025

Coupled EISPH–OSPD Framework for Hydroelastic Response and Brittle Fracture

A unified particle framework couples fluid dynamics, structural response, and brittle fracture for strongly interacting hydroelastic problems.

DOI ↗
First page of the Nuclear Engineering and Technology paper
J9 - 2024

Numerical Investigation of Molten-Corium Spreading Using EISPH

The EISPH method resolves the highly viscous free-surface dynamics and heat transfer that govern molten-corium spreading.

DOI ↗
First page of the Journal of Computational Physics paper
J6 - 2024

Comparative Study of SPH Methods for Multiphase Flow with High Density Difference

WCSPH, EISPH, and EICSPH are systematically compared to identify their accuracy and stability across challenging high-density-ratio multiphase flows.

DOI ↗

1 / 4

Manuscripts Under Review

  1. 2026

    Characterization of Full-Power Steady-State Conditions and Local Multiphysics Phenomena in CABRI Transients Using APOLLO3®/CATHARE3 Under Review

    Hee Sang Yoo, Jonathan Debove, Claire Vaglio-Gaudard, Héloïse Velardo, Jean-Charles Jaboulay, and Jean-Marc Labit

    Nuclear Science and Engineering

Journal Publications

  1. NEW
    172026
    COMING SOON

    A Coupled EISPH–TLSPH–DM Method for Hydroelastic Fluid–Structure Interaction with Quasi-Brittle Fracture

    Jin-Woo Kim, Hee Sang Yoo, Eung Soo Kim, and Min Luo

    Applied Mathematical Modelling, 117275

    DOI ↗
  2. 162026
    Pool boiling regimes and heat-flux curve

    From Water to Dielectric Fluids: Pool Boiling Research under Pressure and Subcooling for Next-Generation Cooling

    Sung Jin Kim, Hyunjin Yong, Hee Sang Yoo, and Il Woong Park

    Renewable and Sustainable Energy Reviews, 239, 116852
    2024 JCR: Top 2.4% · IF 16.3

    DOI ↗
  3. 152026
    First page of the oxidized Zircaloy-4 pool-boiling paper

    Effects of Surface Characteristics of Oxidized Zircaloy-4 on Pool Boiling Heat Transfer

    Sung Jin Kim, Sangmin Song, Junbeom Song, Il Woong Park, Hee Sang Yoo, and Hyun Sun Park

    International Communications in Heat and Mass Transfer, 176, 111277

    DOI ↗
  4. 142026
    Two-dimensional staggered domain decomposition for multi-GPU SPH

    Dynamic Load Balancing for Multi-GPU Smoothed Particle Hydrodynamics Using Two-Dimensional Staggered Domain Decomposition

    Yelyn Ahn, Namjae Choi, Hee Sang Yoo, and Eung Soo Kim

    Advances in Engineering Software, 216, 104123

    DOI ↗
  5. 132026
    COMING SOON

    A Steady-State Eulerian Smoothed Particle Hydrodynamics (SPH) Approach for Incompressible Flow and Heat Transfer Using the Semi-Implicit Method for Pressure-Linked Equations (SIMPLE) Algorithm

    Tae Hwan Kim, Hee Sang Yoo, Jin-Woo Kim, and Eung Soo Kim

    International Journal for Numerical Methods in Engineering, 127(1), e70255

    DOI ↗
  6. 122025
    EISPH and OSPD particle coupling schematic

    Coupled EISPH–OSPD Framework for Modeling Hydroelastic Response and Brittle Fracture

    Hee Sang Yoo and Eung Soo Kim

    Computational Mechanics, 77(4), 1025–1059

    DOI ↗
  7. 112025
    SPH support domain for implicit viscosity solvers

    Comparative Evaluation of Matrix-Free Implicit Viscosity Solvers for GPU-Accelerated SPH Simulation of Highly Viscous Fluids

    Hee Sang Yoo and Eung Soo Kim

    Computational Particle Mechanics, 12, 4107–4130

    DOI ↗
  8. 102025
    SPH kernel and support-domain schematic for impact simulation

    GPU-Parallelized SPH Solver for Accurate Hypervelocity Impact Simulation of Shaped Charge Jet Penetration in Concrete Structures

    Jin Hyun Kim, Hee Sang Yoo, Young Beom Jo, and Eung Soo Kim

    International Journal of Fracture, 249(3), 52

    DOI ↗
  9. 92024
    Computational workflow for molten-corium spreading analysis

    Numerical Investigation of Spreading Phenomena of Molten Corium Using EISPH Method

    Hee Sang Yoo and Eung Soo Kim

    Nuclear Engineering and Technology, 57(4), 103301

    DOI ↗
  10. 82024
    Unified SPH kernel approximation for steam-explosion analysis

    Simulation of Shockwave Propagation Characteristics in Nuclear Reactor Cavity During External Steam Explosion Using Unified SPH

    Jin Hyun Kim, Hee Sang Yoo, Young Beom Jo, and Eung Soo Kim

    Nuclear Engineering and Technology, 57(4), 103274

    DOI ↗
  11. 72024
    COMING SOON

    Dynamic Load Balancing of Multi-GPU Parallelization for VULCANO VE-U7 Corium Spreading Analysis Using SOPHIA

    Yelyn Ahn, Hee Sang Yoo, Namjae Choi, and Eung Soo Kim

    Nuclear Technology, 211(6), 1316–1336

    DOI ↗
  12. 62024
    Comparison of WCSPH and incompressible SPH solution procedures

    Comparative Study of WCSPH, EISPH and Explicit Incompressible-Compressible SPH (EICSPH) for Multi-Phase Flow with High Density Difference

    Hee Sang Yoo, Young Beom Jo, and Eung Soo Kim

    Journal of Computational Physics, 112930

    DOI ↗
  13. 52023
    Eulerian-Lagrangian weakly compressible SPH formulation

    A Simple Eulerian–Lagrangian Weakly Compressible Smoothed Particle Hydrodynamics Method for Fluid Flow and Heat Transfer

    Hee Sang Yoo, Young Beom Jo, Jin Woo Kim, Eung Soo Kim, and Tae Soo Choi

    International Journal for Numerical Methods in Engineering, 124(4), 928–958 Featured Cover ↗

    DOI ↗
  14. 42022
    SPH kernel approximation and particle support domain

    GPU-Based SPH-DEM Method to Examine the Three-Phase Hydrodynamic Interactions Between Multiphase Flow and Solid Particles

    Young Beom Jo, So-Hyun Park, Hee Sang Yoo, and Eung Soo Kim

    International Journal of Multiphase Flow, 153, 104125

    DOI ↗
  15. 32022
    Water-entry simulation of spherical projectiles using SPH

    Effect of Wettability on the Water Entry of Spherical Projectiles: Numerical Analysis Using Smoothed Particle Hydrodynamics

    Hee Sang Yoo, Hae Yoon Choi, Tae Hwan Kim, and Eung Soo Kim

    AIP Advances, 12(3), 035014

    DOI ↗
  16. 22020
    SPH smoothing kernel and support-domain definition

    Development of Multi-GPU-Based Smoothed Particle Hydrodynamics Code for Nuclear Thermal Hydraulics and Safety: Potential and Challenges

    So-Hyun Park, Young Beom Jo, Yelyn Ahn, Hae Yoon Choi, Tae Soo Choi, Su-San Park, Hee Sang Yoo, Jin Woo Kim, and Eung Soo Kim

    Frontiers in Energy Research, 8, 86

    DOI ↗
  17. 12019
    Dry-cask heat-transfer performance with inert-gas mixtures

    Heat Transfer Enhancement in Dry Cask Storage for Nuclear Spent Fuel Using Additive High Density Inert Gas

    Hee Sang Yoo, Seung Hun Yoo, and Eung Soo Kim

    Annals of Nuclear Energy, 132, 108–118

    DOI ↗

Conference Publications

International Conferences

  1. 72026

    Multiphysics Coupling of APOLLO3 and CATHARE3 via the C3PO Platform for Analysis of CABRI Power Transients

    H. S. Yoo, J. Debove, C. Vaglio-Gaudard, E.-Y. Garcia-Cervantes, J.-C. Jaboulay, and J.-M. Labit · PHYSOR 2026 · Turin, Italy · April 19–23, 2026

  2. 62025

    A Smoothed Particle Hydrodynamics Model for Safety Assessment of the Ex-vessel Core Catcher under Reactor Vessel Failure

    J. W. Kim, H. S. Yoo, T. H. Lee, Y. Ahn, M. C. Kwon, and E. S. Kim · NURETH-21 · Busan, Korea · August 31–September 5, 2025 Best Paper

  3. 52025

    Particle-Based Approaches to Multiphysics Simulation in Nuclear Safety

    E. S. Kim, Y. Ahn, J. W. Kim, J. H. Kim, J. Park, Y. B. Jo, and H. S. Yoo · NURETH-21 · Busan, Korea · August 31–September 5, 2025

  4. 42024

    Numerical Investigation on the Safety Assessment of an Ex-vessel Core Catcher under Large-break Reactor Vessel Failures Using Smoothed Particle Hydrodynamics

    J. W. Kim, H. S. Yoo, T. H. Lee, Y. Ahn, M. C. Kwon, and E. S. Kim · The Eleventh Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety · Seoul, Korea · November 10–13, 2024

  5. 32022

    GPU-accelerated Explicit Incompressible-Compressible SPH for multi-phase flow with large density difference

    H. S. Yoo, Y. B. Jo, and E. S. Kim · Proceedings of the SPHERIC Workshop · Catania, Italy

  6. 22018

    Heat Transfer Enhancement of Dry Cask Storage System Using Binary Helium and Heavy Inert Gas Mixture

    H. S. Yoo, S. H. Yoo, and E. S. Kim · The Eleventh Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety · Busan, Korea · November 18–21, 2018

  7. 12017

    The Investigation of Flow Characteristics in 3-Pin Wire-Wrapped Fuel Bundle Using Laser-Based Measurement Techniques

    M. S. Song, H. S. Yoo, J. H. Kim, and E. S. Kim · NURETH-17 · Xi'an, China · September 3–8, 2017

Domestic Conferences

  1. 92026

    CABRI

  2. 82025

    Numerical Analysis of Melting and Interfacial Flow in a Direct-Contact Latent Heat Storage System Reflecting the Marangoni Effect

    M. H. Kim, H. S. Yoo, and I. W. Park · Korean Society for Fluid Machinery · Jeju, Korea · December 4–5, 2025

  3. 72024

    Numerical Investigation of Corium Spreading Phenomena using Smoothed Particle Hydrodynamics

    H. S. Yoo and E. S. Kim · Transactions of the Korean Nuclear Society Spring Meeting · Jeju, Korea · May 9–10, 2024 Best Paper

  4. 62024

    Dynamic Modeling for 20 kWe Heat Pipe Fission Battery with Dual Power Conversion System

    K. J. Park, T. H. Kim, H. S. Yoo, Y. B. Jo, and E. S. Kim · Transactions of the Korean Nuclear Society Spring Meeting · Jeju, Korea · May 9–10, 2024

  5. 52023

    Dynamic Modeling of Free Piston Stirling Generator for Micro Nuclear Reactors

    K. J. Park, T. H. Kim, H. S. Yoo, E. S. Kim, and Y. B. Jo · Transactions of the Korean Nuclear Society Autumn Meeting · Gyeongju, Korea · October 25–27, 2023 Best Paper

  6. 42021

    Development of an Eulerian–Lagrangian Coupling Method Using SPH

    H. S. Yoo and E. S. Kim · Proceedings of the KSCFE Conference · Seoul National University Siheung Campus, Korea

  7. 32021

    Comparative Analysis of Recent Pressure-Noise Reduction Methods for Free-Surface Flow and Fluid–Structure Interaction Using SPH

    H. S. Yoo and E. S. Kim · Proceedings of the KSOE Conference · Busan, Korea

  8. 22021

    Numerical Simulation on Spreading and Impact Behavior of a Single Droplet Using Smoothed Particle Hydrodynamics

    H. S. Yoo, T. H. Kim, and E. S. Kim · Transactions of the Korean Nuclear Society Virtual Autumn Meeting · October 21–22, 2021

  9. 12018

    Thermal Performance Enhancement of Dry Cask Storage System Using Helium-Based Binary Gaseous Mixture

    H. S. Yoo, E. S. Kim, and S. H. Yoo · Transactions of the Korean Nuclear Society Autumn Meeting · Yeosu, Korea · October 25–26, 2018 Best Poster

Software

SOPHIA

A Lagrangian-based HPC-CFD code for versatile thermal-hydraulics and nuclear safety application

NEA-1911 · OECD-NEA Official Repository

Description: SOPHIA is a GPU-enabled, particle-based multiphase flow solver built on smoothed particle hydrodynamics (SPH), Lagrangian discretization, and matrix-free iterative solvers. Designed for high-fidelity thermal-hydraulic analysis of corium spreading, severe accidents, free-surface dynamics, highly viscous multiphase systems, and fluid–structure interaction.

Principal Investigator: Prof. Eung Soo Kim
Co-Developers: Y. B. Jo, S. H. Park, H. Y. Choi, T. S. Choi, S. S. Park, H. S. Yoo, Y. L. Ahn, J. H. Kim, T. H. Lee, H. Chae, J. M. Park, J. R. Kim, D. H. Kim

Join Us

Joining MONAMI Lab

MONAMI 연구실은 원자력 시스템을 더 정확하고 효율적으로 해석하는 계산과학 연구에 관심 있는 학생을 기다립니다. 원자력 열수력, 다물리·다중스케일 해석, 입자 기반 수치해석, GPU 병렬계산 및 디지털트윈 기술에 관심이 있다면 함께 새로운 문제에 도전할 수 있습니다.

MONAMI Lab welcome illustration

Open Positions

  • 학부연구생
  • 석사과정
  • 박사 및 석·박사통합과정

What We Value

수치해석, 프로그래밍 또는 원자력공학 경험은 연구를 시작하는 데 도움이 되지만 필수는 아닙니다. 원자력 계산과학과 시뮬레이션 연구에 관심이 많고, 새로운 문제를 꾸준히 탐구하고 싶은 학생을 기다립니다.

How to Join

아래 지원 설문을 작성해 주세요. 추가 문의는 heesang.yoo@jbnu.ac.kr로 보내주시기 바랍니다. 모집 여부는 시기와 연구실 상황에 따라 달라질 수 있습니다.

Apply via Google Form ↗

Lab Highlights

  • 연구 협력 네트워크
    서울대학교, 경희대학교, 인하대학교, 한양대학교, KAIST 등 국내 주요 대학 및 KAERI, KINS, CEA 등 국내외 원자력 연구기관과 공동연구 및 연구 협력을 추진합니다.
  • 밀도 있는 연구 지도
    학생의 관심과 강점을 바탕으로 연구 주제를 구체화하고, 연구 수행과 논문 작성의 전 과정을 지도교수가 긴밀하게 지도합니다. 연구 주제에 따라 협력 기관의 전문 연구진과 함께 연구할 기회도 제공합니다.

Visit & Contact

Contact Information

Students and researchers interested in MONAMI Lab are always welcome to get in touch.

MONAMI Lab

Room 416, Engineering Building No. 8

Jeonbuk National University

567 Baekje-daero, Deokjin-gu, Jeonju 54896, Republic of Korea

전북특별자치도 전주시 덕진구 백제대로 567
전북대학교 공과대학 8호관 416호

Emailheesang.yoo@jbnu.ac.kr Tel+82-63-270-4993 Google MapsOpen ↗ Kakao MapEngineering Bldg. 8 ↗