Conference Agenda

BEEs: A Multiphysics Simulation Engine for Advanced Nuclear Fuel Innovation

Guanghui Su

Xi’an Jiaotong University, China, People's Republic of

On Flow-Induced Vibrations of Single and Multiple Cylinders in Cross-Flow and using Medium-Resolution Methods for Numerical Predictions

Kevin Zwijsen

Nuclear Research and Consultancy Group, Netherlands, The

A Plan for Developing a Korean Virtual Reactor Platform for SMR Demonstration and Operation

Yun-Je Cho

Korea Atomic Energy Research Institute, Korea, Republic of

Experimental and Numerical Investigation on Thermal-hydraulic Performance of a Novel 3-dimension Corrugated Channel Fluid Flow

Taemin Ahn, Armanto Pardamean Simanjuntak, Jaeyoung Lee

Handong Global University, Korea, Republic of

Measurement of Void Fraction and Wall Heat Transfer Coefficient in the Sub-Cooled and Nucleate Boiling Regime in Steam-Water Two-Phase Flow

Muyue Li¹, Ji Yong Kim¹, Hanxing Sun², Yang Liu², Xiaodong Sun¹

1: University of Michigan, United States of America; 2: Virginia Tech, United States of America

Acoustic Analysis to Identify Boiling Characteristics in the LANL Isotope Production Facility Cooling System

Pei-Hsun Huang¹, Jee Hyun Seong², Jonathan Mario Castro-Aguilar¹, Ellen Margaret O'Brien¹, Christiaan Vermeulen¹

1: Los Alamos National Laboratory, United States of America; 2: Korea Advanced Institute of Science & Technology, Korea, Republic of

High-Speed Imaging and Analysis of Nucleation Site Density on Nuclear Fuel Claddings

Nicolas Wefers¹, Daniel Vlček², Wilson Heiler¹, Stephan Gabriel¹

1: Karlsruhe Istitute of Technology, Institute of Thermal Energy Technology and Safety, Germany; 2: Czech Technical University in Prague, Faculty of Nuclear Sciences and Physical Engineering, Czech Republic

Experimental Investigation of the Internal Structure of Boiling Two-Phase Water Flow under LWR Core Operating Conditions

Jean-Marie Le Corre¹, Haipeng Li², Dmitry Grishchenko², Aleksander Kipiela², Max Persson², Pavel Kudinov², Henryk Anglart²

1: Westinghouse Electric Sweden AB, Sweden; 2: Royal Institute of Technology, Sweden

Experimental Study on Mixed-Convection Wall Friction in Vertical Annular Channels under Natural Circulation Flow

Youngchang Ko, Seongbae Park, Sang Gyun Nam, Jae Jun Jeong, Byongjo Yun

Pusan National University, Korea, Republic of

Scaling Criteria for Wall Boundary Conditions of Free Convective Thin Plates with Volumetric Heat Generation

Moon Won Song, Seong Min Kim

Jeonbuk National University, Korea, Republic of

Natural Convection by Flow Boiling in Inclined Channel

Byeonghee Lee, Seok-Gyu Jeong, Junyoung Kang

Korea Atomic Energy Research Institute, Korea, Republic of

Investigation of Cooling Channel Height Control on Two – Phase Flow Behavior in Natural Circulation Systems

Zumaro Zumaro¹, Ceyda Eldem¹, HangJin Jo^1,2

1: Division of Advanced Nuclear Engineering, POSTECH, Korea, Republic of; 2: Department of Mechanical Engineering, POSTECH, Korea, Republic of

Heat Transfer Correlations for Upward Flow Over Curved Surfaces: Forced and Mixed Convection Regimes

Sameer Osman^1,2, Imran Afgan^1,2, Yacine Addad^1,2

1: Khalifa University of Science and Technology, United Arab Emirate; 2: Emirates Nuclear Technology Center (ENTC), United Arab Emirates

Impacts of Internal Heating on Temperature Distribution in Channels

Lubomir Bures, Per Nilsson

Saltfoss Energy ApS, Denmark

Digital Twins and Separate Effects Loop to Support Operation of a Stable Salt Reactor

Thanh Hua¹, Nathaniel Hoyt¹, Yan Cao¹, Alexander Heifetz¹, Taeseung Lee¹, Konstantinos Prantikos¹, Benjamin Cutrer¹, Won-Sik Yang², Seungug Jae², Hangyu Lee², Luke Godfrey³, Tom Taylor³, Rory O’Sullivan³

1: Argonne National Laboratory, United States of America; 2: University of Michigan, United States of America; 3: Moltex Energy, Canada

Hydrogen Risk Analysis of Aqueous Homogeneous Reactor with Gas Recombination System

Ruicheng Zhong, Ziqiang Zou, Hongping Sun Sun, Yu Liu, Jiagen Wang, Yong Zhang, Zhifang Qiu, Wenpei Feng

Nuclear Power Institute of China, China, People's Republic of

Development of a High-Fidelity Radiative Heat Transfer Model for Assessing Thermal Radiation Influence in Molten Salt Reactors

Mahdi Aghili Nasr¹, Lorenzo Loi¹, Carolina Introini¹, Antonio Cammi^1,2

1: Politecnico di Milano, Italy; 2: Khalifa University, United Arab Emirates

Pressure Drop Experiment in Conical Pebble Bed

Minho Lee, Seth Cadell

Kairos Power, United States of America

Toward Accelerating Transients: Multirate Timestepping and Reduced Order Modeling for Complex Domains

Elia Merzari¹, John Acierno¹, Tri Nguyen¹, Yu-Hsiang Lan², Misun Min³, Paul Fischer²

1: Penn State, United States of America; 2: University of Illinois, United States of America; 3: Argonne National Laboratory, United States of America

How to Achieve Robust CFD Acceleration with Scientific Machine Learning

Shilaj Baral¹, Sangam Khanal¹, Youngkyu Lee², Joongoo Jeon¹

1: Jeonbuk National University, Korea, Republic of; 2: Brown University, United States of America

Development of a Fluid-as-a-Solid Approximation for Modelling Coolant Channels in High Temperature Gas Reactors with Reduced Computational Cost

David Barton, John Harknett, Ryan Tunstall, Ewan Kemish, Chris Ince

Rolls-Royce, United Kingdom

Development of a Physics-Informed Coarse-Mesh Method and Applications to the Thermohydraulic Analysis of Annular Fuel Assembly

Guanqun Ding, Yao Xiao, Hanyang Gu

Shanghai Jiao Tong University, China, People's Republic of

Development of a Multiphysics Model of the ATR Using a Coarse-Mesh Porous Medium Approach

Meredith Eaheart¹, Peter German², Ramiro Oscar Freile², Majdi I. Radaideh¹

1: University of Michigan, United States of America; 2: Idaho National Laboratory, United States of America

Benchmark of System Thermal-hydraulic Codes for the Dip Cooler Instability Facility Test Section

Danilo Caterino¹, Giuseppe Francesco Nallo¹, Antonino Lombardo², Matteo Rostagno², Valeria Parrinello², Giuseppe Spina², Roberto Bonifetto¹

1: Politecnico di Torino, Italy; 2: newcleo SpA, Italy

Experimental Investigation on Convection Heat Transfer Characteristics of Lead–bismuth Eutectic in Circular Tubes Under Natural Circulation

Jieming Hou¹, Kuang Bo¹, Wei Chen², Shirui Li³

1: Shanghai Jiao Tong University, China, People's Republic of; 2: Wuhan University of Science and Technology, China, People's Republic of; 3: China Institute of Atomic Energy, China, People's Republic of

A Thermal-hydraulic Simulation Model and Control Modeling of a Lead-bismuth Reactor based on Numap Software

Xinheng Zhao, Minjun Peng, Chunyuan Niu

Harbin Engineering University, China, People's Republic of

Simulation of NACIE Benchmark Tests with the SAS4A/SASSYS-1 Code

Anton Moisseytsev

Argonne National Laboratory, United States of America

Numerical Study on the Influence of Rough Surfaces on Flow and Heat Transfer Characteristics in Narrow Rectangular Channels Cooled by Liquid Metals

Xue Zhang¹, Wenpei Feng^1,2, Xiaolong Yang², Shangdong Yang²

1: Nuclear Power Institute of China, China, People's Republic of; 2: Chengdu University of Technology, China, People's Republic of

Review of Direct Air Capture Applying to the Nuclear System

Seongmin Son, Taejun Song, Joohung Jung

Kyungpook National University, Korea, Republic of

Design Characteristics and Preliminary Performance Analysis on Passive Safety System of i-SMR

Seong-Su Jeon, Younjae Park, Sang Gyun Nam, Jehee Lee, Jan Hruškovič, Soon-Joon Hong, Bub Dong Chung

FNC Technology, Korea, Republic of

Adaptive Decay Heat Estimation for Non-SCRAM Shutdowns: Verification and Application

Evgeny Nikitin

Helmholtz-Zentrum Dresden-Rossendorf, Germany

The Impact of Inventory Fill on Large-Scale RCCS Performance At PassiveBoiloff Conditions

Matthew Jeffrey Jasica, Qiuping Lv, Darius Lisowski

Argonne National Laboratory, United States of America

Investigation of Performance of a Large-Scale Water-Based RCCS Under Varying Decay Heat Loads

Qiuping Lv, Matthew J. Jasica, Darius D. Lisowski, Zhiee J. Ooi, Rui Hu

Argonne National Laboratory, United States of America

Variational Bayesian Last Layer Augmented Recurrent Neural Networks for Transient Thermal Hydraulic Experiments

Logan Alexander Burnett¹, Umme Nabila¹, Izabela Gutowska², Majdi Radaideh¹

1: University of Michigan Ann Arbor, United States of America; 2: Oregon State University, United States of America

BF-GAN: Development of an AI-driven Bubbly Flow Image Generation Model Using Generative Adversarial Networks

Wen Zhou¹, Shuichiro Miwa¹, Yang Liu², Koji Okamoto¹

1: The University of Tokyo, Japan; 2: Virginia Tech, United States of America

Extracting Bubble Information in Nucleate Boiling Using a Deep Learning Approach

Ungjin Na¹, Bruno Pinheiro Serrao², Junyoung Seo³, Youngjoon Suh⁴, Hangjin Jo^1,3, Juliana Pacheco Duarte², Yoonjin Won⁴

1: Department of Mechanical Engineering, Pohang University of Science and Technology (POSTECH), Korea, Republic of; 2: University of Wisconsin-Madison, United States of America; 3: Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Korea, Republic of; 4: University of California, United States of America

A Holistic Segmentation of Boiling Heat Transfer Features Using U_NET based Convolutional Neural Network

Hyoung Suk Yu¹, Matthew Hughes³, Gustavo Matana Aguiar³, Guanyu Su*², Matteo Bucci³, Yong Hoon Jeong¹

1: Korea Advanced Institute of Science and Technology, Korea, Republic of; 2: University of California Berkeley, United State of America; 3: Massachusetts Institute of Technology, United State of America

A Novel Parametric Proper Orthogonal Decomposition Framework for Thermal-Hydraulic Simulations of Once-Through Steam Generators

Yifan Xu¹, Introini Carolina², Riva Stefano², Xiaobo Zeng¹, Minjun Peng¹, Chenyang Wang¹, Genglei Xia¹, Cammi Antonio^3,2

1: Harbin Engineering University, China, People's Republic of; 2: Politecnico di Milano, Italy; 3: Khalifa University, United Arab Emirates

The IAEA Benchmark on Transition from Forced to Natural Circulation with NACIE Heavy Liquid Metal Loop

Ivan Di Piazza¹, L. Ren², X. Xu², R. Zhang³, H. Li³, D. Zhang³, A. Batta⁴, A.G. Class⁴, M. Rajendrakumar⁵, A.K. Chauhan⁵, G. Dhrumil⁵, K. Natesan⁵, D. Martelli¹, P. Lorusso¹, F. Lodi¹, P. Cioli Puviani¹, T. Del Moro¹, R. Da Vià¹, M. Tarantino¹, F. Giannetti⁶, C. Ciurlini⁶, G. Caruso⁶, B. Calgaro⁷, K. Zeng⁸, P. Stefanini⁹, A. Pucciarelli⁹, N. Forgione⁹, O. Abedelhalim⁹, J. Han¹⁰, Y. Jung¹⁰, B. Ha Park¹⁰, F. Roelofs¹¹, M.M.M.D. Hussain¹¹, F. Pangukir¹¹, A. Mathur¹¹, D. Dupleac¹², M. Mladin¹³, C. Dobrinoiu¹³, A. Baisov¹⁴, A. Zalesov¹⁴, I. Aulov¹⁴, A. Vlasenko¹⁵, E. Moiseenko¹⁵, O. Ilyasova¹⁵, N. Mosunova¹⁵, V. Vereshchagin¹⁶, A. Ekimov¹⁶, A. Moiseev¹⁶, K. Sergeenko¹⁶, L. Golibrodo¹⁶, A. Krutikov¹⁶, A. Zefirova¹⁶, E. Biiushkina¹⁶, K. Mikityuk¹⁷, D. Shaver¹⁸, A. Moisseytsev¹⁸, J. Liao¹⁹, N. Virgili²⁰, V. Kriventsev²⁰

1: ENEA, Italy; 2: CIAE, China, People's Republic of; 3: XJTU, China, People's Republic of; 4: KIT, Germany; 5: IGCAR, India; 6: UniRoma La Sapienza, Italy; 7: Newcleo, Italy; 8: NINE, Italy; 9: UniPi, Italy; 10: KAERI, Korea, Republic of; 11: NRG, Netherlands; 12: PUB, Romania; 13: RATEN ICN, Romania; 14: Gidropress, Russian Federation; 15: IBRAE RAN, Russian Federation; 16: NIKIET, Russian Federation; 17: PSI, Switzerland; 18: ANL, United States of America; 19: Westinghouse, United States of America; 20: IAEA, Austria

CFD Validation on Liquid Metal Flow in 19 Wire Wrapped Bundle Flow Investigated in the IAEA Coordinated Research Project CRP-I31038 Using NACIE Experimental Data

Abdalla Batta, Andreas G. Class

Karlsruher Institut für Technologie (KIT), Germany

CFD Benchmark for Non-uniform Heating Experiments in NACIE Rod Bundle

Akshat Mathur¹, Konstantin Sergeenko^2,3, Ivan Di Piazza⁴, Vladimir Kriventsev⁵, Ming Jin⁶, Shize Ouyang⁶, Danna Zhou⁶, Haoyang Li⁷, Dalin Zhang⁷, Abdalla Batta⁸, Andreas G. Class⁸, Aleksander Grah⁹, Roberto Da Vià⁴, Pietro Cioli Puviani^4,10, Andrea Pucciarelli¹¹, Ossama Halim¹¹, Yohan Jung¹², Ferry Roelofs¹, Dhrumil Ganatra¹³, Amit Kumar Chauhan¹³, Rajendrakumar Murugesan¹³, Natesan Kumaresan¹³, Andrei Moiseev², Luka Golibrodo^2,3, Alexey Krutikov^2,3, Anna Zefirova²

1: NRG, Netherlands, The; 2: NIKIET, Russian Federation; 3: JSC PRORYV, Russian Federation; 4: ENEA, Italy; 5: IAEA, Austria; 6: IANS, China, People's Republic of; 7: Xi'an Jiaotong University, China, People's Republic of; 8: KIT-ITES, Germany; 9: JRC, European Commission; 10: Politecnico di Torino, Italy; 11: University of Pisa, Italy; 12: KAERI, Korea, Republic of; 13: IGCAR, India

Development and Testing of High-Temperature Heat Pipes for Micro Modular Reactors: Initial Findings from the MISHA Project

Ruggero Meucci, Rudi Kulenovic, Jörg Starflinger

Universität Stuttgart - Institute for Nuclear Energy and Energy Systems, Germany

Strategic Collaboration between CNL and KAERI on Small Modular Reactor Safety Thermal-Hydraulics

Sun-Kyu Yang¹, Robert Bowden¹, Penny Neal¹, Andrew Morreale¹, Ali Siddiqui¹, Kyoung-Ho Kang², Ki-Yong Choi²

1: Canadian Nuclear Laboratories, Canada; 2: Korea Atomic Energy Research Institute, Korea, Republic of

Application of the Repas Methodology to Analyze the Reliability of the EHRS in the Decay Heat Removal Strategy for an SMR

Erik Cilia¹, Gianmarco Grippo¹, Lorenzo Tempesta¹, Marcello Savini¹, Fulvio Mascari²

1: University of Bologna, Italy; 2: ENEA Bologna Research Center, Italy

Experimental Characterization of Upper Plenum Natural Circulation Phenomena Under Steady State Transient Accident Conditions

Tristen Jeda Rogers, Yassin Hassan, Ryan Sanchez

Texas A and M University, United States of America

Characterization of Coupling Interactions between Passive Safety Systems in Deep Pool Heating Reactors

Feng Shou^1,2, Zhang Yankun^1,2, Zhu Di^1,2, Sun Rulei^1,2, Gao Puzhen^1,2, Tian Ruifeng^1,2, Tan Sichao^1,2

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

Novel Heat Transfer Models to Improve the Performance Prediction of Passive Residual Heat Transfer Systems

Tahmineh Adili, Yu Zhang, Iurii Dolganov, Stephan Leyer

University of Luxembourg, Luxembourg

Numerical Analysis of Natural Circulation and Heat Transfer Dynamics in a Horizontal Reactor Assembly Cooled by Helium-Xenon Mixture

Tianshi Wang¹, Jinyu Wang², Zhongchun Li², Dongchuan Su², Xiang Chai¹, Xiaojing Liu¹

1: Shanghai Jiao Tong University, China, People's Republic of; 2: Nuclear Power Institute of China, China, People's Republic of

Experimental Investigation on Boiling Heat Transfer and Microlayer Dynamics based on Synchronized Visualization

Wei Zhang, Ji Wang, Weishi Peng, Jinbiao Xiong

Shanghai Jiao Tong University, China, People's Republic of

Liquid Film and Droplets Measurements in Upward Annular Two-Phase Flow

Peter Iascone¹, Eymon Lan¹, Richard Tardio¹, Shanbin Shi¹, Devlin Harvey², Ayden Cohn², Yang Liu²

1: Rensselaer Polytechnic Institute, United States of America; 2: Virginia Polytechnic Institute and State University, United States of America

Simultaneous Annular Flow Film Measurement with Total Internal Reflection Method, X-ray Attenuation and Conductivity Film Sensor

Matteo Grasso^1,2, Victor Petrov^1,2, Annalisa Manera^1,2

1: ETH Zürich, Switzerland; 2: PSI, Switzerland

Multidimensional Measurements of Void Oscillations of Subcooled Flow Boiling on a Simulated Offshore Floating Plant

Yutaka Ikeda, Shota Ueda, Takahiro Arai, Riichiro Okawa, Kenetsu Shirakawa, Masahiro Furuya, Atsushi Ui

Central Research Institute of Electric Power Industry, Japan

Analysis of Total Internal Reflection Method (TIRM) Annular Flow Experiments with Accuracy Estimation Aided by an Optical Ray Tracing Simulation

Matteo Grasso^1,2, Valerio Bürgi¹, Victor Petrov^1,2, Annalisa Manera^1,2

1: ETH Zürich, Switzerland; 2: PSI, Switzerland

Experimental investigation of Upward Flow Boiling in a Narrow Annular Channel

Noor Ahmed, Taiyang Zhang, Caleb S. Brooks

University of Illinois Urbana Champaign, United States of America

Experimental Study of Single-phase Flow and Heat Transfer Characteristics of Narrow Rectangular Channels with Non-uniform Heating

Di Zhu, Shixuan Wang, Shou Feng, Rulei Sun, Sichao Tan, Ruifeng Tian

Harbin Engineering University, China, People's Republic of

Numerical Simulation of Flow Boiling in Narrow Rectangular Channels with a Flow Regime transition Model

Qianqian Ma, Guangliang Chen, Xiang Zhang

Harbin Engineering University, China, People's Republic of

Analytical Approach for Flow Reversal in Narrow Rectangular Channels

Basar Ozar, Jeremy Licht

Argonne National Laboratory, United States of America

Numerical Analysis of the Thermal and Hydraulic Characteristics of Mini Channels Incorporating Inter-Connection Mixing Zones

Armanto Pardamean Simanjuntak, Taemin Ahn, Joohan Bae, Jaeyoung Lee

Handong Global University, Korea, Republic of

SAM Code Performance Improvement by Incorporating a High-order Staggered-grid Finite Volume Method

Ling Zou, Rui Hu

Argonne National Laboratory, United States of America

Comparative Analyses of DRACCAR and TRACE Codes for RefloodingThermal-Hydraulics at Low Pressure or Low Flowrate

Andreas Tatidis, Weimin Ma, Sean Roshan

Royal Institute of Technology (KTH), Sweden

Comparative Analysis of RELAP5 and ANSYS-CFX Simulations for Microchannel Heat Exchangers: A Case Study on the VLF Primary Heat Exchanger

Giorgio Khalil Youssef^1,3, Andrea Missaglia², Marco Caramello³, Stefano Lorenzi², Marco Ricotti², Cristiano Ciurluini¹, Fabio Giannetti¹

1: Sapienza University of Rome, Italy; 2: Politecnico di Milano, Italy; 3: Ansaldo Nucleare, Italy

Comprehensive Evaluation of the Applicability of the Relap5 Boron Transport Module in Reactor Annular Down-comer

Qi Zhang¹, Zhenhai Liu¹, Guangliang Yang¹, Yongzhong Huang¹, Junxian Cao¹, Di Wu², Sichao Tan²

1: Nuclear Power Institute of China, China, People's Republic of; 2: Harbin Engineering University, China, People's Republic of

Performance Evaluation of State-of-the-art drift-flux Model Implemented in AMAGI

Naofumi Tsukamoto¹, Takashi Hibiki²

1: Nuclear Regulation Authority, Japan; 2: City University of Hong Kong, Hong Kong S.A.R. (China)

Benchmarking on the Performance of System Codes to Reproduce a Long SBO Sequence with the Actuation of a Passive Heat Removal System

Jordi Freixa¹, Víctor Martínez-Quiroga¹, Aymane Talha¹, Fares Alblouwy², Maxime Vernassiere³, Guillaume Mianné⁴, Sebastian Buchholz⁵, Jong Hyuk Lee⁶, Buyng-Gil Huh⁷, Omar Al-Yahia⁸, David Blanco de las Muelas⁹, Michael Johansson¹⁰, Miguel Sánchez-Perea¹², Martina Adorni¹³, Simon Schollenberger¹¹, Lars Dennhardt¹¹

1: Universitat Politècnica de Catalunya, Spain; 2: Technical Research Center of VTT, Finland; 3: French Alternative Energies and Atomic Energy Commission (CEA), France; 4: Electricité de France (EdF), France; 5: Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH (GRS), Germany; 6: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of; 7: Korea Institute of Nuclear Safety (KINS), Korea, Republic of; 8: Paul Scherrer Institut (PSI), Switzerland; 9: Polytechnic University of Valencia - Energy Engineering Institute (UPV), Spain; 10: Vattenfall Nuclear Fuel, Sweden; 11: Framatome GmbH; 12: Consejo de Seguridad Nuclear (CSN), Spain; 13: OECD Nuclear Energy Agency (NEA)

Application of Subchannel Analysis to NACIE Pin Bundle

Francesco Lodi¹, Zhihao Ren², Wang Ze², Rong Zhang³, Haoyang Li³, Dalin Zhang³, Ivan Di Piazza¹, Roberto Da Vià¹, Fabio Giannetti⁴, Cristiano Ciurluini⁴, Gianfranco Caruso⁴, Luca Ammirabile⁵, Mirea Mladin⁶, Cristina Dobrinoiu⁶, Akhmed Baisov⁷, Artem Zalesov⁷, Andrey Vlasenko⁸, Anton Ekimov⁹, Andrei Moiseev⁹, Elena Biiushkina⁹, Konstantin Sergeenko⁹, Anton Moisseytsev¹⁰, Rachel Thomas¹⁰, Daniel J. O'Grady¹⁰, Jun Liao¹¹, Nicole Virgili¹², Vladimir Kriventsev¹²

1: ENEA, Italy; 2: CNPRI, Italy; 3: XJTU, China; 4: UniRoma La Sapienza, Italy; 5: EC-JRC; 6: RATEN ICN, Romania; 7: Gidropress, Russian Federation; 8: IBRAE RAN, Russian Federation; 9: NIKIET, Russian Federation; 10: ANL, United States of America; 11: Westinghouse, United States of America; 12: IAEA

Development of a Subchannel Thermal-Hydraulics Analysis Code for the Natrium^® Demonstration Reactor

Dustin Langewisch, Sterling Harper, Stephen Palzewicz, Ricky Dehner, SuJong Yoon

TerraPower, LLC, United States of America

Coupled Simulation for Pin-wise Reactor Core Using Subchannel Analysis Code CUPID with Neutron Kinetic and Fuel Performance Code

Yeonghun Lee¹, Kyuseok Sim¹, Youho Lee¹, Hyoung Kyu Cho¹, Jae Ryong Lee²

1: Seoul National University, Korea, Republic of; 2: Korea Atomic Energy Research Institute, Korea, Republic of

Validations of a New Subchannel Analysis Code for the Next Generation BWR Fuel Bundles - Void Fraction and Two-phase Pressure Drop in Single-tube and Rod Bundle -

Yuki Narushima, Takuji Nagayoshi, Kenichi Katono

Hitachi, Ltd., Japan

Minimum Film Thickness Estimations in BWR Fuel Assemblies by Applying a Method to Partition the Liquid Flow in the Annular Flow Regime with the Subchannel Code CTF

Daniel Vincent Mazzone^1,2, Omar Al-Yahia¹, Ivor Clifford¹, Annalisa Manera^1,2

1: Paul Scherrer Institute (PSI), Switzerland; 2: ETH Zürich, Switzerland

Implementation and Verification of the Plate-Type Fuel Heat Structure in the Sub-Channel Thermal-Hydraulics Code CTF

Wonkyo Cho, Agustin Abarca, Maria Avramova

North Carolina State University, United States of America

Numerical Simulation of Aerosol Dispersion Characteristics after Nuclear Power Plant Accident

Nuo Chen, Qinrui Zhang, Mingjun Wang, Hanrui Qiu, Guanghui Su, Wenxi Tian

Xi'an Jiaotong University, People's Republic of China

Analysis of Small Break LOCA of ACME Based on SCENES

Qichao Ma, Hao Zhang, Meng Zhao, Yanhua Yang

Shanghai JiaoTong University, China, People's Republic of

Simulating Molten Corium Concrete Interaction: A Multiphase Approach with OpenFOAM

Kamran Mahboob, Ahmed AlKaabi, Yacine Addad

Khalifa University, United Arab Emirates

Computational Study of Helium Bubble Dynamics in Molten Salt via Coupled VOF and Neutronics Multi-physics Framework

Seungsu Han¹, Antonio Cammi², Hyungdae Kim¹

1: Kyung Hee University, Korea, Republic of; 2: Politecnico di Milano, Italy

Simulation of Noble Metal Behavior in Molten Salt from a Molecular Dynamics Perspective

Jiaqi Chen¹, Caleb S. Brooks²

1: University of Shanghai for Science and Technology, China, People's Republic of; 2: University of Illinois Urbana Champaign, United States of America

Coupled Two-Phase Flow and Thermochemistry Modeling in Pronghorn for Molten Salt Tritium Breeding Blanket Analysis

Samuel Walker, Mauricio Tano, Parikshit Bajpai, David Reger

Idaho National Laboratory, United States of America

Benchmark of Eulerian-Lagrangian Methods for Solid Fission Product Tracking inside Molten Salt Reactor

Tommaso Pernatsch¹, Stefano Lorenzi¹, Rocco Moretti²

1: Politecnico di Milano, Italy; 2: NAAREA, Nanterre, France

The Investigation of Noble Metal Mass Transfer Efficiency to Circulating Bubbles with Surfactants

Huihua Yang¹, Qiyun Cheng¹, Ling Zou², Rui Hu², Wei Ji¹

1: Rensselaer Polytechnic Institute, United States of America; 2: Argonne National Laboratory,United States of America

Verification, Validation, and Uncertainty Quantification Study of Mo-99 Deposition onto a Cylinder in a Molten Salt Reactor

Logan Stewart Brown, Mark Kimber

Texas A&M University, United States of America

Experimental Investigations on Fuel Pin Failure Propagation in Lead-cooled Fast Reactor Cores

Axel Monney^1,2, Victor Petrov^1,2, Annalisa Manera^1,2

1: ETH Zurich, Switzerland; 2: Paul Scherrer Institut (PSI), Switzerland

Study on the Drift Flux Model of Gas-LBE Two-phase Flow in Circular Tubes with Different Diameters

Hong Zhang¹, Yangyong Ou², Di Wang², Lingfeng Wan¹, Wan Sun¹, Liangming Pan¹, LongXiang Zhu¹

1: Chongqing University, China, People's Republic of; 2: China Nuclear Power Technology Research Institute Co., Ltd, China, People's Republic of

Study on the Interfacial Area Concentration of Nitrogen-Lead-Bismuth-Alloy Two-Phase Flow

Lingfeng Wan^1,2, Yong Ouyang³, Di Wang³, Hong Zhang^1,2, Longxiang Zhu^1,2, Zaiyong Ma^1,2, Liangming Pan^1,2

1: Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, China, People's Republic of; 2: Department of Nuclear Engineering and Technology, Chongqing University, China, People's Republic of; 3: China Nuclear Power Technology Research Institute, China, People's Republic of

Data-Driven Bubble Transport Prediction and Uncertainty Quantification in LFR During SGTR with Heterogeneous Inputs and Constrained Outputs

Longcong Wang¹, Kejian Dong², Jiyun Zhao²

1: Harbin Engineering University, China, People's Republic of; 2: City University of Hong Kong, Hong Kong S.A.R. (China)

Interaction Mechanism between Lead-bismuth Liquid Metal and Water

Lin Zhang, Chang Deng, Xiaojing Liu

Shanghai Jiao Tong University, China, People's Republic of

Enhancement of Inherent Safety Performance in Lead-Bismuth Fast Reactors Through Secondary-Side Passive Residual Heat Removal System

Rongtian Zeng, Li Ge, Jianqiang Shan

Xi'an Jiaotong University, China, People's Republic of

Accelerating Microreactor Deployment with Hardware-in-the-Loop Augmented Digital Twin

Austin Michael Warren, Trevor Kent Howard

Oregon State University, United States of America

Transient Response of a Vertical Low-Temperature Heat Pipe

Ilyas Yilgor, Sungbeen Park, Shanbin Shi

Rensselaer Polytechnic Institute, United States of America

Design and Experimental Analysis of Intermediate Heat Exchanger for Heat Pipe Cooled Reactor Using Fiber Optic Sensor

Yongnam Lee¹, Suwon Lee¹, HangJin Jo^1,2

1: Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, Korea, Republic of; 2: Department of Mechanical Engineering, Pohang University of Science and Technology, Korea, Republic of

Verification and Validation of 2-D Transient Heat Pipe Thermal Analysis Code with Melting/Solidification Model

Ye Sung Kim, Myung Jin Jeong, Hyoung Kyu Cho

Seoul National University, Korea, Republic of

Multi-physics Coupled Analysis of the Heat Pipe-cooled Reactor Based on OpenFOAM

Zeqin Zhang, Ruiyu Han, Chenglong Wang, Cheng Chen, Cheng Wang, Haocheng Zhao, Kailun Guo, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su

Department of Nuclear Science and Technology, State Key Laboratory of Multiphase Flow Engineering, Shaanxi Key Lab of Advanced Nuclear Energy and Technology

CFD Analysis of CHF Characteristics in Vertical and Inclined Tubes

Yujiao Peng, Huanjun Kong, Ya Li, Jianqiang Shan, Miao Gui

Xi'an Jiaotong University, China, People's Republic of

Evaluation of Rod-Bundle Critical Heat Flux using MARS-KS Subchannel Analysis

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

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

Assessment of CTF Performance against Critical Heat Flux Rod Bundle Database

Vinicius de Melo Monteiro, Juliana Pacheco Duarte

University of Wisconsin-Madison, United States of America

Assessment of CTF for Steady-state and Transient Post-CHF Conditions

Robert K Salko, Vineet Kumar, Nathan A Capps

Oak Ridge National Laboratory, United States of America

Uncertainity Quantification and Model Improvement in CTF for Dryout and Reflood Models

Vineet Kumar, William Gurecky, Robert Salko

Oak Ridge National Laboratory, United States of America

Multi-field Simulations of Liquid Film Dryout in Rod Bundle Geometry

Cole Jacob Dunbar¹, Roman William Morse², Jean Marie Le Corre³, Juliana Pacheco Duarte¹

1: University of Wisconsin-Madison, United States of America; 2: Massachusetts Institute of Technology, United States of America; 3: Westinghouse Electric Sweden AB, Sweden

Towards New Experiments for Natural Convection at High Rayleigh Numbers: Definition, Sizing and Analysis Using CFD

Antoine Morente¹, Juan Uribe¹, Sofiane Benhamadouche¹, Pauline Rotach¹, Michael Montout¹, Jean-Luc Vacher², Myeong-Seon Chae³, Domenico Paladino³

1: EDF R&D, France; 2: DISC - Direction Technique, EDF, France; 3: Paul Scherrer Institut (PSI), Switzerland

Natural Convection Heat Transfer Around the Dome with Various Truncation Angles at High Rayleigh Numbers

Suyeon Park, Donghyuk Park, Bumjin Chung

KyungHee University, Korea, Republic of

Surrogate Modelling of Perturbed Natural Circulation in a Simple Test Loop

Patrick Martin Lewis, Heather Davies, Sophie Brown

Rolls Royce, United Kingdom

Flow Visualization of Local Heating Effects in a Molten Salt Natural Circulation Loop

Thomas Scott Carson, Joseph Seo, Hansol Kim, Yassin Hassan

Texas A&M University, United States of America

Design of a Two-Phase Molten Salt Natural Circulation Loop Based on Scaling Laws and Preliminary Analysis Using OpenFOAM

Won Jun Choi, Jae Hyung Park, Sinho Kim, JinHo Song, Sung Joong Kim

Hanyang University, Korea, Republic of

Steady-State Behaviour of Two-Phase Natural Circulation Systems

Latika Dixit, Vijayan P.K., Satya Sekhar Bhogilla

Indian Institute of Technology Jammu, India

Spray-cooling Heat Transfer of a Hot Tank Wall

Kristian Patrik Angele

Vattenfall AB, Sweden

A Molecular Dynamics Study on Pore Structure: Performance Comparison between Metal Foam and Artificial Mesh Porous Surface

Wei Deng, Pengcheng Zhao, Tao Yu

University of South China, China, People's Republic of

Water Entrainment at T-junctions - Numerical Simulations, Experimental Data, and Scaling Approach

Alexandre Guyot

EDF (Electricité de France), France

Experimental Study on the Heat Transfer Characteristics of Rotating Heat Pipes for Motor Rotor Cooling

Zhanghao Zhu^1,2, Song Zhang^1,2,3, Xin Ma^1,2, LangLang Tian^1,2, Jidong Chen^1,2, Simiao Tang^1,2, Wan Sun^1,2, Luteng Zhang^1,2, Liangming Pan^1,2

1: Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, China, People's Republic of; 2: Department of Nuclear Engineering and Technology, Chongqing University, China, People's Republic of; 3: Wuhan Marine Electric Propulsion Research Institute, China, People's Republic of

An Investigation of the Deposition Mechanism of Corrosion Products under Nucleate Boiling Conditions

Hongkang Tian, Tenglong Cong, Hanyang Gu

Shanghai Jiao Tong University, China, People's Republic of

The Contribution of Deterministic and Statistical Sampling Methodologies to the Conservatism of BEPU Results

Mengyan Hu, Wenxuan Wang, Zongyang Li, Jun Yang

Huazhong University of Science and Technology, China, People's Republic of

Thermal Hydraulic Analysis of PKL Facility During Multi-Steam Generator Tube Rupture (MSGTR)

Omar S. Al-Yahia, Ivor Clifford, Hakim Ferroukhi

Paul Scherrer Institut, Switzerland

Experimental Study of Thermal Radiation in a Large PANDA Vessel with Steam Content Variation

Yago Rivera¹, Ralf Kapulla¹, Nabil Ghendour¹, Domenico Paladino¹, Sidhart Paranjape², Myeong-seon Chae¹, Simon Suter¹, Christopher Hug¹

1: Paul Scherrer Institute, Switzerland; 2: Eastern Switzerland University of Applied Sciences, Switzerland

Experimental Study for Multidimensional ECC Behaviors in Downcomer Annulus with Direct Vessel Injection Mode during the LBLOCA Reflood Phase

Xin Ma^1,2, Jie Wan^1,2, Wan Sun^1,2, Zaiyong Ma^1,2, Luteng Zhang^1,2, longxiang Zhu^1,2, Qiang Lian^1,2, Simiao Tang^1,2, Liangming Pan^1,2

1: Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, China, People's Republic of; 2: Department of Nuclear Engineering and Technology, Chongqing University, China, People's Republic of

Study on the Response of the Internal Structure of In-vessel Pressurizer under Ocean Conditions

Xue He^1,2, Zixuan Quan^1,2, Haoyu Ruan^1,2, Dongyang Li^1,2, Sichao Tan^1,2, Ruifeng Tian^1,2

1: Heilongjiang Provincial Key Laboratory of Nuclear Power Plant Performance and Equipment, Harbin Engineering University, China, People's Republic of; 2: Key Laboratory of Advanced Nuclear Energy Technology of Ministry of Industry and Information Technology, Harbin Engineering University, China, People's Republic of

Experimental and Numerical Investigations of Thermal Radiation Effects in the Medium-Scale LINX Facility

Nabil Ghendour, Abdelouahab Dehbi, Ralf Kapulla, Domenico Paladino, Yago Rivera Durán, Wilhelm-Martin Bissels, Myeongseon Chae, Simon Manuel Suter, Christoph Hug

Paul Scherrer Institute (PSI), Switzerland

Two-phase Flow Structure in a Header and Feeder Pipe System under Simulated Large Break Loss-of-coolant Accidents

Zhuoran Dang, Lan-Qin Yuan, Jun Yang, Liqian Li

Canadian Nuclear Laboratories, Canada

Improving the Understanding and Prediction of Mixed Convection of Developing Flow

Zewen Zou, Shuisheng He

University of Sheffield, United Kingdom

Enabling Advanced Gas-cooled Reactor Life Extension by Predicting Through-Life Pressure and Temperature Fields in Graphite Using CFD

Graham Macpherson¹, Carolyn Howlett¹, Ross Higgins¹, David Munn¹, James Pethan², Mike Rabbitt²

1: Frazer-Nash Consultancy, United Kingdom; 2: EDF Nuclear Services, United Kingdom

Cost-Effective Simulation of a Prismatic HTGR Fuel Assembly Using Subchannel CFD

Bo Liu, Wei Wang, Charles Moulinec, Stefano Rolfo

Science and Technology Facilities Council (STFC), United Kingdom

Modeling a Sodium Heat Pipe Experiment at SPHERE Using Sockeye

Joshua Edmund Hansel¹, Zachary Don Sellers¹, Jeremy Lee Hartvigsen¹, Piyush Sabharwall¹, Lise Cecile Madeleine Charlot¹, Elia Merzari²

1: Idaho National Laboratory, United States of America; 2: The Pennsylvania State University, United States of America

Study on Nuclear-thermal-structural Multi-physics Coupling in Solid-state Heat Pipe Reactors Considering Irradiation Effects

Dacai Zhang, Zeguang Li, Zilin Su, Huifu Wang, henglong Lin

Tsinghua University, China, People's Republic of

System Level Modeling of the 200 MW General Pebble Bed Reactor (GPBR200) with SAM

Zhiee Jhia Ooi, Ling Zou, Thanh Hua, Jun Fang, Rui Hu

Argonne National Laboratory, United States of America

Deposition Characteristics of Particles in Printed-Circuit Heat Exchangers based on Dynamic Mesh Method

Qi Sun, Haifeng Liu, Zixuan Zhang, Xiaozhong Wang, Wenkui Ma, Gang Zhao, Xiaoyong Yang, Wei Peng

Tsinghua University, China, People's Republic of

Establishment of a Mechanism-data Hybrid Driving Model of Shell-and-tube Heat Exchanger based on MWORKS/Modelica

Chunyuan Niu, Minjun Peng, Xinheng Zhao

Harbin Engineering University, China, People's Republic of

Numerical Design Framework for the PCHE Heat Exchanger in the Supercritical CO2 Brayton Cycle

Jianxin Qiao

Southeastern University, China, People's Republic of

Surrogate-based Shape Optimization of Airfoil Fin PCHE based on the FFD Method

Tong Liu

Nuclear Power Institute of China, China, People's Republic of

Impact of Nodalization on Performance Analysis of Helical Steam Generator

Semin Joo, Junha Hwang, Taeyeon Min, Jeong Ik Lee

Korea Advanced Institute of Science and Technology, Korea, Republic of

Thermal-Hydraulic Assessment of the Water-Cooled Lithium-Lead Test Blanket Module Water Cooling System via OpenModelica

Michael McDermott¹, Shuisheng He¹, Chris Harrington², Nakul Sashidharan², James Bailey²

1: The University of Sheffield, United Kingdom; 2: United Kingdom Atomic Energy Authority, United Kingdom

Modeling and Simulation for Primary Loop of a Low-Temperature Nuclear Heating Reactor Based on Modelica

Lu Wanlu¹, Zhang Wenwen¹, Hao Wentao¹, Li Weihua^1,2, Yang Xingtuan^1,2, Liu Baoting², Jiang Zhenjiao², Huang Xingguan²

1: Tsinghua Univesity, China, People's Republic of; 2: General Clean Energy Co.,Ltd., China, People's Republic of

0-D Modelling and Analysis of Heat Transfer for Medical Isotope Production of 211-At

James Robert Vulcanoff, Alexander Coxe, Skye Thurston, Lane Carasik

Virginia Commonwealth University, United States of America

Dynamic Response of Vortex Induced Vibration-Suppression Using Non-Linear Energy Dissipation

Ahmed Abuelyamen¹, Mariam Nagi Amer¹, Ahmed K. Alkaabi^1,2, Saeed A. Alameri^1,2, Imran Afgan^1,2

1: Department of Mechanical and Nuclear Engineering, College of Engineering, Khalifa University, United Arab Emirates; 2: Emirates Nuclear Technology Center, Khalifa University of Science and Technology, United Arab Emirates

Contact Thermal Resistance Model for Solid-solid Heat Transfer Interface Based on Helium Gas Filling

Ersheng You^1,2, Tianmi Wang^1,2, Yiyi Li^1,2, Jianjun Xu^1,2, Zhangrui Yan^1,2, Xingjie Ren³

1: National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, China, People's Republic of; 2: CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, China, People's Republic of; 3: Shandong University, China, People's Republic of

Research on Power Measurement and Analysis of In-Pile Irradiation Device in HFETR

Jinkang Cheng, Yun Wang, Liang Zhang, Shuai Jin, Jin Lei, Yixiong Sun

Nuclear Power Institute of China, China, People's Republic of

Validation of Scaling Laws for Investigating the Thermal Behavior of Sodium Heat Pipes in Microreactors

Dong Hun Lee, In Cheol Bang

Ulsan National Institute of Science and Technology, Korea, Republic of

Numerical Investigation of Filling Ratio Effects on Heat Pipe Performance: Modified Conduction Model

Faruk Celik, In Cheol Bang

Ulsan National Institute of Science and Technology, Korea, Republic of

Numerical Study of Heat Transfer Characteristics of High Temperature Heat Pipe with Wire Mesh Wick

Qishi Sun¹, ZhiPeng Zhang¹, Kailun Guo¹, Hao Sun², Chenglong Wang¹, Kui Zhang¹, Xiaoqiang He³, Wenxi Tian¹, Suizheng Qiu¹, Guanghui Su¹

1: Xi'an Jiaotong Unversity, China, People's Republic of; 2: China Nuclear Power Technology Research Institute, China, People's Republic of; 3: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, China, People's Republic of

Development of the Modular Passive-cooling Tower Equipped with a Wickless Heat Pipe for Long-term Cooling of a SMR

Yonadan Choi¹, Min Suk Lee², Yong Hoon Jeong¹

1: KAIST, Korea, Republic of; 2: Texas A&M University, United States of America

Design and Analysis of a 20-kW Free-Piston Stirling Generator for Microreactors

Phat Doan, Minghui Chen

The University of New Mexico, United States of America

Study on Intermittent Boiling Phenomena During Sodium Heat Pipe Startup

Yinghuan Cui, Jianjun Xu, Tianzhou Xie, Zhangrui Yan

Nuclear Power Institute of China, China, People's Republic of

Overview of Key Elements of Combustible Gases Management in Containment

Ahmed Bentaib¹, Gonzalo Jiménez², Luis Enrique Herranz³, Nabiha Chaumeix⁴, Stephan Kelm⁵, Ernst-Arndt Reinecke⁶, Matthias Braun⁷, Marco Koch⁸, Ivo Kljenak⁹, Oleksandr Sevbo¹⁰, Zhe {Rita} Liang¹¹

1: IRSN, France; 2: UPM, Spain; 3: CIEMAT, Spain; 4: CNRS-ICARE, Spain; 5: JULICH, Germany; 6: JULICH, Germany; 7: Framatome, Germany; 8: RUB, Germany; 9: JSI, Solvenia; 10: Energorisk, Ukraine; 11: CNL, Canada

Assessment of Monitoring Performance for Hydrogen Concentration in Severe Accidents

Youngsu Na, Jin-Hyeok Kim, Changwan Kang, Seongho Hong

Korea Atomic Energy Research Institute, Korea, Republic of

PARs Interaction with Other Safety Systems during Severe Accidents in Western PWR Containments

Joan Fontanet, Luis Enrique Herranz

CIEMAT, Spain

Validation of the PAR Model REKO-DIREKT in the Framework of the AMHYCO Project

Ernst-Arndt Reinecke, Claudia Druska

Forschungszentrum Juelich GmbH, Germany

Hydrogen Behavior Analysis for Lower Level of BWR Reactor Building during Severe Accident

Tomohisa Yuasa, Miki Saito, Kimitoshi Yoneda

Central Research Institute of Electric Power Industry, Japan

Experimental Study on the Containment Thermal Hydraulic Behaviors by Hydrogen Mitigation and Pressure Control Systems at Severe Accident Conditions

Jongtae Kim, Seongho Hong, Ki Han Park, Jinhyeok Kim, Jeong Yun Oh, Sang Ho Kim

Korea Atomic Energy Research Institute, Korea, Republic of

Development of a Machine Learning Model for Predicting the Long-term Coolability of Ex-vessel Debris Beds for Extension of Systemcode Modelling

Nicole Richter, Juliane Neuhaus, Marco K. Koch

Ruhr-Universität Bochum, Germany

Shallow Recurrent Decoders for State Estimation in Parametric Accidental Scenarios of Circulating Fuel Nuclear Reactors

Stefano Riva¹, Carolina Introini¹, J. Nathan Kutz², Antonio Cammi^1,3

1: Politecnico di Milano, Italy; 2: University of Washington, United States of America; 3: Khalifa University, United Arab Emirates

Development of an Auxiliary Surrogate Model for Refined Prediction of Severe Accident Progression: Oscillation Prediction Model

Taeyeon Min¹, Semin Joo¹, Seok Ho Song¹, Jeong Ik Lee¹, Mi Ro Seo²

1: KAIST, Korea, Republic of; 2: KHNP CRI, Korea, Republic of

Development of Surrogate Model for Reactor Cooling System based on ASTEC Simulations during the Early Phase of Station Blackout

Christophe D'Alessandro¹, Terttaliisa Lind¹, Seolsonghwa Song²

1: Paul Scherrer Institute, Switzerland; 2: Chung-Ang University, Korea, Republic of

Break Size Prediction Model for Small Modular Reactors Based on Explainable Artificial Intelligence and Hyperparameter Optimization

Dingyu Jiang, Hexin Wu, Zhenlan Wang, Junli Gou, Jianqiang Shan

Xi'an Jiaotong University, China, People's Republic of

Safety Evaluation of Multiple Steam Generator Tube Rupture Events with BEPU Analysis and Explainable AI

Tran Nguyen¹, Aya Diab²

1: Dalat Nuclear Research Institute, Dalat, Vietnam; 2: Ain Shams University, Cairo, Egypt

Hydrogen Production by Steam Reforming Technology Using HTGR or SMR

Huang Zhang, Chengye Wu, Zhiyi Peng, Junyi Wang, Huaqiang Yin

Tsinghua University, China, People's Republic of

Evaluating Hydrogen Production by Electrolysis Coupled with Passive Molten Fast Salt Reactor (PMFR)

Jihun Im¹, Jae Hyung Park¹, Seungmin Lee¹, JinHo Song¹, Sung Joong Kim^1,2

1: Department of Nuclear Engineering, Hanyang University, Korea, Republic of; 2: Institute of Nano Science & Technology, Hanyang University, Korea, Republic of

Development and Analysis of the ARC Fusion Reactor Integrated Solar-based Energy System: Both Electrical and Non-electrical Applications for Hydrogen Production and Desalination

Sulenur Asal, Adem Acir

Gazi University, Turkiye

Experimental Thermal Performance Evaluation of a Sodium Heat Pipe Assembly for Space Nuclear Reactors

Sin-Yeob Kim, Byung-Ha Park, In-Woo Son, Chan-Soo Kim

Korea Atomic Energy Research Institute, Korea, Republic of

Re-entry Thermal Testing for Nuclear-Powered Thermoelectric Generators in Space Using 0.4MW Plasma Jet Facility

Moon Won Song, Philyong Oh, Gunwoo Choi

Jeonbuk National University, Korea, Republic of

Multiphysics Coupling Simulation and Output Characteristics Analysis of Thermionic Space Reactor TOPAZ-II

Jianwei Wang, Xufan Han, Li Ge, Jianqiang Shan

Xi’an Jiaotong University, China, People's Republic of