Conference Agenda

Numerical Simulation and Sensitivity Analysis of Condensation-Induced Water Hammer in Steam Generator Blowdown System

Rui Zhang, Jiaming Zhao, Wentao Guo, Shengfei Wang, Li Peng, Jiannan Shen, Danfeng Zhao, Xiaoxia Chen

China Nuclear Power Engineering Co., Ltd, China, People's Republic of

A Priori Modelling of the Temperature Variance Dissipationtransport Equation

Corina Sanz Souhait¹, Jean-François Wald¹, Sofiane Benhamadouche¹, Rémi Manceau²

1: EDF R&D, France; 2: CNRS, Universite de Pau et des Pays de l’Adour, INRIA, France

Analysis of Surface Temperature Distribution on Micro-Pillar Structures Using Fiber Optic Sensors under Pool Boiling Conditions

Minkyu Park¹, Hyeon Taek Nam¹, Seongro Lee², Euijae Kim³, Jae-Ho Lee³, Donghwi Lee^1,4

1: Graduate School of Mechanical-Aerospace-Electric Convergence Engineering, Jeonbuk National University, Korea, Republic of; 2: Department of Mechanical Engineering, Jeonbuk National University, Korea, Republic of; 3: KEPCO Nuclear Fuel Co.,Ltd., Korea, Republic of; 4: Department of Mechanical System Engineering, Jeonbuk National University, Korea, Republic of

Bubble Growth Characteristics on a Moving Wall

Sohyeun Kang, Jaejun Kim, Minseop Lee, Daegyoum Kim

KAIST, Korea, Republic of

Numerical Study of the Dynamic Response of RCS Boron Concentration during Dilution Operation

Xiangyu Chi, Jiazhuo Wang, Pei Yu, Jiazhi Liu, Jiaming Zhao, Yaru Li

China Nuclear Power Engineering Co., Ltd., China, People's Republic of

Reverse Forces on Check Valve Obturators Produced by Geometric Parameter Combinations – a DOE Study

Tsolag Apelian, Genesis Ponce

Curtiss Wright, United States of America

The Cross Section Generation Method based on Deep Learning for Neutronics and Thermal Hydraulics Coupling

Lu Cao¹, Lipeng Wang¹, Duoyu Jiang¹, Tianliang Hu¹, Huaqi Li¹, Hailong Huang¹, Zhouyu Liu², Liangzhi Cao²

1: Northwest Institute of Nuclear Technology, China, People's Republic of; 2: Xi’an Jiaotong University, China, People's Republic of

A Study on PAFS Heat Transfer Performance Prediction Using Korean Thermal-hydraulic System Codes

Kyungho Nam, Hyunjoon Jeong

Korea Hydro & Nuclear Power Central Research Institute, Korea, Republic of

Vertical Mini-Channel Multiphase Flow Model Simulation and Experiment

Witiwat Jiragoontansiri¹, Taeseok Kim², Florian Chavagnat¹, Arunkumar Seshadri¹, Koroush Shirvan¹

1: Massachusetts Institute of Technology, United States of America; 2: Jeju National University, Korea, Republic of

Development and preliminary verification of system analysis models and code for Small Lead-based cooled fast reactor Based on modelica

Tian Xiaoyan, Li Huaqi, Li Da, Shi LeiTai, Chen Lixin, Zhu Lei, Chen Sen, Luo Xiaofei

Northwest Institute of Nuclear Technology, China, People's Republic of

Analysis of MSGTR Accident with PAFS at the ATLAS Experimental Facility Using the MARS-KS and SPACE Code

Hyunjoon Jeong, Kyungho Nam

Korea Hydro & Nuclear Power Co., LTD. Central Research Institute, Korea, Republic of

Review and Analysis of the Passive Heat Removal System Experimental Facility for Validation of the Robustness Assessment Methodology

Jehee Lee¹, Seong-Su Jeon¹, Nhan Hien Hoang¹, Ju-Yeop Park²

1: FNC Technology co., LTD., Korea, Republic of; 2: Korea Institute of Nuclear Safety, Korea, Republic of

Numerical Simulation of Single Boiling Bubble Generation with Implicit Microlayer Model and Explicit Transition Region under Conjugated Heat Transfer

Zuzhi Li, Jonghwi Choi, Hyungdae Kim

Kyung Hee University, Korea, Republic of

The Numerical Study of the Thermal-hydraulic Characteristics of the In-containment Storage Rack

Yaru Li, Yanyu Sun, Shuliang Huang

China Nuclear Power Engineering Co.,Ltd., China, People's Republic of

Investigation of Flow Mixing Characteristics in APR1000 Reactor Flow Model Based on Turbulence Models

Uiju Jeong

KHNP Central Research Institute, Korea, Republic of

Comparative Study on the Effect of Heat Transfer and Steam Fraction on Safety Valve through CFD Analysis

Ji Su Kim, Hui Un Ha, Kwan Geun Lee, Jae Yoon Jeong, Hyun Suk Nam, Kyoung Uk Lee, Seok Jong Yoon, Uiju Jeong, Dae Hun Kim

KHNP, Korea, Republic of

Impact of Fin Height and Side Slot Design on Cooling Performance of Hypervapotron Technique

Iljin Kim¹, Gubin Lee², In-Yeop Kang², Hyungdae Kim²

1: Korea Atomic Energy Research Institute, Korea, Republic of; 2: Kyung Hee University, Korea, Republic of

Numerical Investigation on Phase Separation Characteristics of Bubbly Flow in Horizontal T-Junction

Wang Fupeng^1,2, Zhu Di^1,2, Sun Rulei^1,2, Wang Shixuan^1,2, Tan Sichao^1,2, Tian Ruifeng^1,2

1: State Key Laboratory of Marine Thermal Energy and Power, China, People's Republic of; 2: Harbin Engineering University, China, People's Republic of

Application of SPACE/CUPID/MASTER Coupled Code: Main Steam Line Break Accident

Chiwoong Choi, Ik-kyu Park, Jaeseok Heo, Kwiseok Ha

KAERI, Korea, Republic of

Design and Development of Separate and Integral Effects Test Facilities for Licensing and Deployment of Advanced Water-Cooled Small Modular Reactors

Kenneth Lee Fossum¹, Grant Hendrickson¹, Palash Kumar Bhowmik¹, Justin Thales Johnson¹, Piyush Sabharwall¹, Clay Lietwiler²

1: Idaho National Laboratory, United States of America; 2: Holtec International, United States of America

Lucky Loop - A Thermal Hydraulic Experiment to Create Data for Validation of Modern Codes

Tilmann Schlitt¹, Christian Reiter¹, Mackenzie Wilson²

1: FRM II / TUM, Germany; 2: McMaster University, Canada

Experimental Study on an Intermediate Break Loss of Coolant Accident (IBLOCA) under the OPR1000 Operation Condition

Yusun Park, Byoung Uhn Bae, Jae Bong Lee, Seok Cho, Jong Rok Kim, Jun Yeong Jung, Kyoung Ho Kang, Seung Wook Lee

KAERI, Korea, Republic of

Heating and Cooling System Design of the Separate Effect Test Facility for Flow-Accelerated Corrosion and Erosion (SEFACE) Studies in Liquid Lead

Haipeng Li, Max Persson, Ignas Mickus, Dmitry Grishchenko, Pavel Kudinov

KTH Royal Institute of Technology, Sweden

Integral Effect Test and Code Analysis on the Cooling Performance of the PAFS during a SLB Accident

Jongrok Kim, Seok Cho, Byoung-Uhn Bae, Jae Bong Lee, Yusun Park, Kyoung-Ho Kang

Korea Atomic Energy Research Institute, Korea, Republic of

Experimental Study of Oxidized Cladding Effects on Fuel Cladding Behavior During Reflood Phase Using Thermo-Mechanical and Thermal-Hydraulic Coupled Experiment

Jongrok Kim, Kihwan Kim, Jae-Bong Lee, Jong-Kuk Park, Young-Jung Youn, Hae Seob Choi, Byung-jun Lim, Sang-Ki Moon, Seok Kim

Korea Atomic Energy Research Institute, Korea, Republic of

Study on Effects of Pressurizer Spray and Heater on Pressurizer Level Control System Malfunction Event of APR1000 Using SPACE Code

Ye Eun An, Sang Jin Lee, Jisu Kim, Se Young Ro, Min Shin Jung, Ung Soo Kim

KEPCO Engineering & Construction Company, Inc., Korea, Republic of

Numerical Analysis of Hydrogen Recombination under Natural Convection Condition between Two Vertical Flat Catalytic Plates

Dae-Hyun Kim¹, Stephan Kelm², Ernst-Arndt Reinecke², Youngsu Na³, Dong-Wook Oh¹

1: Chosun University, Korea, Republic of; 2: Forschungszentrum Juelich GmbH, Institute of Energy Technologies (IET-4), Germany; 3: Korea Atomic Energy Research Institute, Korea, Republic of

CFD Modeling for Ring Type Fuel Spacers in Sleeveless HTGRs Core Design

Yusuke Yamazaki, Yosuke Nishimura, Koji Okamoto

The University of Tokyo, Japan

Numerical Analysis of Low-leakage Molten Salt Spreading behavior and Solidification in NaCl-KCl-UCl3

Ye Hwan Chun¹, Jae Hyung Park¹, Sang Mo An², Sung-Il Kim², JinHo Song¹, Jae Min Han¹, Sung Joong Kim^1,3

1: Hanyang University, Korea, Republic of; 2: Korea Atomic Energy Research Inst., Korea, Republic of; 3: Institute of Nano Science and Technology, Hanyang University, Korea, Republic of

Research on Data-Physics Hybrid-driven Core Temperature Reconstruction of Heat Pipe Reactors

Pengzhi Zhang, Zeguang Li, Huifu Wang, Henglong Lin, Zilin Su

Tsinghua University, Department of Engineering Physics, Beijing 10003, China, People's Republic of

Development Status of Standard Design for Passive Safety System in i-SMR

Chang Hun Lee, Seok Ho Lee, Hui Un Ha, Seok Jong Yoon, Ji Su Kim, Dong Won Jeong, Dae Hun Kim

Central Research Institute, Korea Hydro Nuclear Power, Korea, Republic of

Improving Initialization of ASTEC's Thermal-Hydraulic Solver with Machine Learning-Based Methods for Enhanced Convergence in Severe Accident Simulations

Marcello Savini^1,2, Raphael Monod³, Simone Gianfelici², Bastien Poubeau³, Fulvio Mascari²

1: Alma Mater Studiorum - Università di Bologna, Italy; 2: ENEA, Italy; 3: IRSN, France

Comparative Evaluation of Advanced PINN Techniques for Efficient Fluid Dynamics Modeling

Hanseul Kang, Kin Wing Wong

KTH Royal Institute of Technology, Sweden

Enhancing Critical Heat Flux Prediction in Fuel Rod Bundles with Interpretability Transformer Architectures

Bin Han¹, Siwei Qi¹, Xiaoliang Zhu¹, Bao-Wen Yang²

1: Southeast University, China, People's Republic of; 2: DEQD, China, People's Republic of

Modeling of Sodium Heat Pipes for Microreactors Passive Cooling

Riccardo Luigi Sansone^1,2, JunSoo Yoo³, Victor Petrov^1,2, Annalisa Manera^1,2

1: ETH Zurich, Switzerland; 2: Paul Scherrer Institut, Switzerland; 3: Idaho National Laboratory, United States of America

Experimental Evaluation of the Buckling of a Single Cylindrical Plate

Alexander Hans Westerberg¹, Wade Marcum¹, Aaron Weiss¹, Guanyi Wang², Cezary Bojanowski², Andrew Hebden²

1: Oregon State University, United States of America; 2: Argonne National Laboratory, United States of America

Flow Pattern Analysis of Printed Circuit Heat Exchangers with Zigzag Channels Using PIV Visualization and CFD

Yoomyeong Lee¹, Jaejun Hyun¹, Seongmin Lee², Hong Beom Park², Kyoungwoo Seo², Donghwi Lee^1,3

1: Graduate School of Mechanical-Aerospace-Electric Convergence Engineering, Jeonbuk National University, Korea, Republic of; 2: Korea Atomic Energy Research Institute, Korea, Republic of; 3: Department of Mechanical System Engineering, Jeonbuk National University, Korea, Republic of

Dynamic Simulation and Performance Analysis of a Nuclear-solar Energy System with Thermal Energy Storage

Xinyu Li^1,2, Yan Liu^1,2, Xiang Chai^1,2, Xiaojing Liu^1,2

1: Shanghai Jiao Tong University, China, People's Republic of; 2: Shanghai Digital Nuclear Reactor Technology Integration Innovation Center, China, People's Republic of