Conference Agenda

Validation of Thermal Hydraulic Tool for Modeling the Natural Convection of a Molten Salt Flow Loop

Andres Nicolas Fierro Lopez^1,2, Guillaume Giudicelli², Mauricio Tano Retamales², Ethan Rozak¹, Cole Gentry¹, Kevin Clarno¹

1: The University of Texas at Austin, United States of America; 2: Idaho National Laboratory, United States of America

Integrated Multiphysics Framework with Species Transport to Support Advanced Molten Salt Reactor Technologies in Pronghorn

Mauricio Tano, Samuel Walker, Piyush Sabharwall, Ramiro Freile, Rodrigo de Oliveira, David Reger

Idaho National Laboratory, United States of America

High-Fidelity Modelling of the Molten Salt Fast Reactor

Maximiliano Dalinger, Elia Merzari, Saya Lee, Casey Emler

Pennsylvania State University, United States of America

Flow Distribution in a Molten Salt Reactor and its Dependency on Support Grid Designs

Levi Schilter¹, Mark Kimber¹, Jack Crooks², Thomas Provencher², Peter Pizzato²

1: Texas A&M University, United States of America; 2: Zachry Nuclear, Inc., United States of America

CFD-Based Investigation of Flow and Heat Transfer Characteristics of Molten Salt with Internal Heat Source

Hui Deng^1,2, Shanwu Wang¹, Chong Zhou¹, Siqin Hu¹, Shuaiyu Xue¹, Pinyan Huang^1,2, Hongxiang Yu^1,2

1: Shanghai Institute of Applied Physics, Chinese Academy of Sciences Shanghai, China, People's Republic of; 2: University of Chinese Academy of Sciences, China, People's Republic of

Impact of Neutronics-thermal-hydraulics Coupling on the Wall Temperature Fluctuations in Liquid Fuel Reactors

Max Begue¹, Axel Laureau¹, Elsa Merle¹, Julien Vukasin²

1: CNRS / LPSC, France; 2: Orano DRD, France

An Analytical Method to Model Interfacial Heat and Mass Transfer in Multi-field CFD Codes

Clément Loiseau^1,2, Stéphane Mimouni^1,2, Didier Colmont¹, Stéphane Vincent²

1: EDF R&D, France; 2: MSME, Université Gustave Eiffel, France

Next-Generation Thermal Network Computation: Implementing Generalized 3D Resistance Modeling with Random Forest Predictors in Pebble Bed Reactor Systems

Yiyang Luo¹, Nan Gui¹, Qian Wang¹, Xingtuan Yang¹, Jiyuan Tu^1,2, Shengyao Jiang¹

1: Tsinghua University, China, People's Republic of; 2: RMIT University, Australia

Study on the Multi-Physics Coupling Mechanism of CRUD with a Zeta Potential-Regulated Corrosion Product Particle Deposition Model Based on Dynamic Mesh Technology

Guangchao Yang^1,2, Xiaojing Liu^1,2, Wei Zeng³, Jie Wang³, Hui He^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; 3: Nuclear Power Institute of China, China, People's Republic of

Local Reynolds Number and Prandtl Number Dependent Thermal Wall Function Development based on DNS Data of a Turbulent Boundary Layer Flow

Jure Oder, Ioana Gocea, Lilla Koloszar

von Karman Institute for Fluid Dynamics, Belgium

CFD Modelling of a CANDU Irradiated Fuel Bay

Qi Chen, Krishna Podila, Andrew Morreale

Canadian Nuclear Laboratories, Canada

Design and Analysis of a Gas Sparging Mass Transfer Experiment for Tritium Removal in Molten Salt Reactor Applications

Andrew S Hutsell, Ryan P Mcguire, Ethan M Villareal, Jeremy I Lopez, Lane B Carasik

Virginia Commonwealth University, United States of America

Downscaling of a Prototypical Reactor Cavity Cooling System for a Molten Salt gFHR for Laboratory-scale Experimentation

Minghui Chen, Khaled Talaat

The University of New Mexico, United States of America

Loss-of-Forced-Circulation Experiments in a Reduced-Scale Integral Effects Test Facility to Verify Inherent Safety of the Kairos Power Fluoride Salt Cooled High Temperature Reactor

Griffen Latimer, Seth Cadell, Craig Gerardi, Lambert Fick, Jadyn Reis, Ka-Yen Yau

Kairos Power, United States of America

Integral Effect Tests and System Thermal Hydraulics Code Analyses on the Decay Heat Removal Systems of the STELLA 2 Facility

Yong-Hoon Shin, Seungjoon Baik, Yong Bum Lee, Jung Yoon, Hyeonil Kim, Jewhan Lee

Korea Atomic Energy Research Institute, Korea, Republic of

Influence of the Intermediate Heat Exchanger Geometry on the Flow in a Model Representative of a Sodium Fast Reactor

David Guenadou, Philippe Aubert, Jean-Philippe Descamps

CEA, France

Advanced AMESIM CODE-Based System Transient Safety Analysis for PGSFR

Seon Gon Kim¹, Je Whan Lee², Jae Ho Jeong¹

1: Chung-Ang University, Korea, Republic of; 2: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of

Applicability Investigation of Reactor Vessel Thermal–Hydraulics Analysis Method for Transient Toward Natural Circulation Condition

Erina Hamase¹, Yasuhiro Miyake², Yasutomo Imai², Norihiro Doda¹, Ayako Ono¹, Masaaki Tanaka¹

1: Japan Atomic Energy Agency, Japan; 2: NDD Corporation, Japan

Assessment of a System-level Numerical Model of the Thermal Hydraulic Experimental Test Article (THETA) Facility Using SAS4A/SASSYS-1

Yeongshin Jeong¹, Lander Ibarra¹, Matthew Weathered¹, Daniel J. O'Grady¹, Acacia J. Brunett¹, Rachel Thomas¹, Tyler Sumner¹, Lisa Momkus², James McCay², Ryan Blanchard², Patrick Everett²

1: Argonne National Laboratory, United States of America; 2: Oklo Inc., United States of America

ATHLET Simulation of the SMR-SFR Primary System: Exploring 0D and Pseudo-3D Flow Modeling

Alexander Ponomarev, Emil Fridman

Helmholtz Zentrum Dresden Rossendorf (HZDR), Germany

IAEA's Current Efforts in Advancing Reactor and Nuclear Fuel Technologies

Anzhelika Khaperskaia, Alexei Miassoedov

IAEA, Austria

Numerical Modeling of CRUD Layer for Investigating Thermal Limit in PWR-Type Nuclear Power Plant

Ju Hun Jung, In Cheol Bang

Ulsan National Institute of Science and Technology (UNIST), Korea, Republic of

Study of Passive Safety Injection of Core Makeup Tank and Analysis of the Influencing Factors

Junxiao Yang, Chengcheng Deng, Yi Huang

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

CATHARE Code Assessment of Steam Line Break Scenario with Passive Auxiliary Feedwater Cooling

Anis Bousbia Salah

Bel V, Belgium

Thermal Behavior of a PHWR Channel with an Eccentric Pressure Tube in an Oxidizing Environment

Ketan Ajay¹, David Novog¹, Ravi Kumar², Deb Mukhopadhyay³

1: McMaster University, Canada; 2: Indian Institute of Technology Roorkee, India; 3: Bhabha Atomic Research Centre, India

Numerical Simulation Study on the Flow and Heat Transfer Characteristics of 3×3 Helical Cruciform Fuel Assemblies under Non-uniform Power Density

QiongTao Li, QianNi Duan, Wei Li, JunMei Wu

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

Finite Element Analysis of Force and Deformation Characteristics of a Wire-wrapped Fuel Rod Bundle under Large Temperature Gradient

Mingyue He^1,2, Zaiyong Ma^1,2, Liangming Pan^1,2, Qiang Lian^1,2, Longxiang Zhu^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

Challenges in Simulating Swirl Flow in Externally Cooled Safety Injection Dead-End Pipe Connected to RPV

Martin Draksler, Iztok Tiselj

Jožef Stefan Institute, Slovenia

Benchmarking Low-Power Pressurized Conduction Cooldown Transient in the High Temperature Test Facility

Thanh Hua¹, Ling Zou¹, Robert Kile², Aaron Epiney², Sungnam Lee³, Tariq Jafri⁴, Xianmin Huang⁴, Geoffrey Waddington⁴, Fajar Pangukir⁵, Marek Stempniewicz⁵, Ferry Roelofs⁵, Gusztav Mayer⁶, Zsombor Bali^6,7

1: Argonne National Laboratory, United States of America; 2: Idaho National Laboratory, United States of America; 3: Korea Atomic Energy Research Institute, Korea, Republic of; 4: Canadian Nuclear Laboratories, Canada; 5: Nuclear Research and Consultancy Group, The Netherlands; 6: HUN-REN Centre for Energy Research, Hungary; 7: Budapest University of Technology and Economics, Hungary

High-Fidelity Numerical Investigation of the Initial Stages of Pressurized Hydrogen Jet Release

Odie Aziz Nassar¹, Moran Ezra¹, Marcel Martins Alves¹, Sergey Kudriakov², Etienne Studer², Liel Ishay³, Yoram Kozak¹

1: Tel Aviv University, Israel; 2: DES/ISAS-DM2S-STMF, CEA, Université Paris-Saclay, Gif-sur-Yvette, France; 3: Nuclear Research Center Negev, Israel

Grid Independence Test on the Lower Plenum Mixing Test of the High Temperature Test Facility Benchmark

Mohammed Muaaz Mohamed Dilshad Hussain, Ferry Roelofs

NRG PALLAS, Netherlands, The

Multiscale Thermal-hydraulic Analysis of the MARVEL Micro-reactor Using Coupled MOOSE Subchannel (SCM) and SAM

Vasileios Kyriakopoulos, Lise Charlot, Mauricio Tano, Guillaume Giudicelli, Joshua E. Hansel

INL, United States of America

Evaluation of Air and sCO₂ Brayton Cycle for Heat Pipe-Cooled Micro Modular Reactor

Matthias Peiretti, Michael Buck, Jörg Starflinger

University of Stuttgart, Germany

A Feasibility Study of Physics-Informed Neural Network-Based Severe Accident Analysis Code

Jeesuk Shin¹, Minseo Lee¹, Cheolwoong Kim², Sunwoong Yang³, Joongoo Jeon¹

1: Jeonbuk National University, Korea, Republic of; 2: Hanyang University, Korea, Republic of; 3: Korea Advanced Institute of Science and Technology, Korea, Republic of

Development of Physical Properties Prediction Model Near Critical Point Using Deep Learning

Jubin Kim¹, Sai Raja Gopal Vadlamudi², Eung Soo Kim¹, Hyun Sun Park¹

1: Seoul National University, Korea, Republic of; 2: Helmholtz-Zentrum Dresden-Rossendorf, Germany

Evaluation of RCS and SG Injection Effectiveness in the Extended SBO Scenario of the OPR-1000

Jemo Ryu, Jaehyun Cho

Chung-Ang University, Korea, Republic of

Simulation Study of Coolant Loss Accident in Floating Nuclear Power Platform based on IP200

Lei Yu, Yifan Xu, Genglei Xia, Minjun Peng

Harbin Engineering University, China, People's Republic of

B4C-Stainless Steel Eutectic Characterisation and Boron Migration under Severe Reactor Conditions

Zeeshan Ahmed¹, Ravinder Kumar¹, Hidemasa Yamano², Marco Pellegrini^1,3, Ryo Yokoyama¹, Koji Okamoto¹

1: The University of Tokyo, Japan; 2: Japan Atomic Energy Agency, Japan; 3: Politecnico di Milano, Italy

Enhanced Anomaly Detection in Liquid Sodium Cold Trap Operation with Synchronization of Time Series of Multi-Modal Sensors

Alexandra Gabrielle Akins^1,2, Xu Wu², Derek Kultgen¹, Alexander Heifetz¹

1: Argonne National Laboratory; 2: North Carolina State University

Sensor Data Prediction in the High Temperature Test Facility with Recurrent Neural Networks

Farhana Farha¹, Meredith Eaheart¹, Izabela Gutowska², Brendan Kochunas¹, Majdi Radaideh¹

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

Verification and Validation of Shallow Recurrent Decoders for State Estimation in the DYNASTY Facility

Stefano Riva¹, Andrea Missaglia¹, 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

Toward Developing Machine-Learning-Aided Tools for the Thermomechanical Monitoring of Nuclear Reactor Components

Luiz Carlos Aldeia Machado¹, Victor Coppo Leite¹, Elia Merzari¹, Roberto Ponciroli², Lise Charlot³, Lander Ibarra², Arthur Motta¹

1: The Pennsilvanya State University, United States of America; 2: Argonne National Laboratory, United States of America; 3: Idaho National Laboratory, United States of America

Boiling Water Reactor Core Stability Analysis: Modeling of Out-of-Phase Oscillations using TRACEv5p9/PARCSv3.4.3

Bárbara Navarro, Teresa Barrachina, Rafael Miró, Gumersindo Verdú

Universitat Politècnica de València, Spain

Experimental Investigation of Heaving Motion Effect on Flow Boiling CHF with Axially Cosine-shaped Power Profile Heater

Ja Hyun Ku¹, Heepyo Hong¹, Hyukjae Ko¹, Gi Won Bae¹, Jin-Seong Yoo², Goon-Cherl Park¹, Hyoung Kyu Cho¹

1: Seoul National University, Korea, Republic of; 2: ETH Zürich, Switzerland

Study on the Performance of Improved Gyroid TPMS Structure Heat Exchanger

Nailiang Zhuang, Yangyang Li, Qiqian Zhai, Xiaopeng Zhao, Hangbin Zhao

Nanjing University of Aeronautics and Astronuatics, China, People's Republic of

A Lagrangian-Lagrangian Elastic Body-Incompressible Flow Calculation Method (MPH-MPH) for Fluid-Deformable Structure Interaction

Ryo Yokoyama, Shuichiro Miwa, Koji Okamoto

The University of Tokyo, Japan

Surrogate-Based Multi-Objective Design Optimization of Tree-Shaped Fins with Uniform Branch End Distribution for Latent Heat Thermal Energy Storage

Hansol Kim, Joseph Seo, Yassin Hassan

Texas A&M University, United States of America

Thermal-hydraulic Analysis of Energy Storage and Intermediate Heat Transfer Systems for Tokamak Fusion Reactors

Francesco Colliva¹, Cristiano Ciurluini¹, Bruno Gonfiotti², Amelia Tincani², Fabio Giannetti¹

1: Sapienza University of Rome, Nuclear Engineering Research Group (NERG), Italy; 2: ENEA Brasimone Research Centre, Italy