Conference Agenda

Spacer Grid Rewet during Reflood andModeling Challenges for Thermal-Hydraulic Codes

Stephen M. Bajorek¹, Yue Jin², Fan-Bill Cheung³

1: United States Nuclear Regulatory Commission, United States of America; 2: University of Missouri, United States of America; 3: Pennsylvania State University, United States of America

From Data to Trust: High-Resolution Thermohydraulic Experiments for Future Reactors

Victor Petrov^1,2,3, Annalisa Manera^1,2,3

1: Paul Scherrer Institute, Switzerland; 2: ETH Zurich, Department of Mechanical and Process Engineering, Switzerland; 3: University of Michigan– Ann Arbor, United States of America

Particle-Based Approaches to Multiphysics Simulation in Nuclear Safety

Eung Soo Kim¹, Yelyn Ahn¹, Jin Woo Kim¹, Jin Hyun Kim¹, Juryong Park¹, Young Beom Jo², Hee Sang Yoo³

1: Seoul National University, Korea, Republic of; 2: Kyung Hee University, Korea, Republic of; 3: CEA/DES/IRESNE, France

Development of Wall Convective Heat Transfer Model in the Dispersed Flow Film Boiling Regime based on Quasi-steady-state Experiments

Kyung Mo Kim¹, Joseph Kelly², Stephen Bajorek², Xiaodong Sun³

1: Korea Institute of Energy Technology (KENTCH), Korea, Republic of; 2: University of Michigan, United States of America; 3: The U.S. Nuclear Regulatory Commission, United States of America

Evaluation of RELAP’s Post Critical Heat Flux Behaviour for Uncertain Parameter Quantification and Analysis

Pablo Osés, Jordi Freixa, Germán López

Technical University of Catalonia (UPC), Spain

Effect of the Initial Cladding Temperature and Subcooling on the Quench Temperature during Single Rod Reflood Experiment

WooHyun Jung¹, Nicolas Fox¹, Cole Dunbar¹, Kumar Sridharan¹, Michael Corradini¹, Hwasung Yeom²

1: University of Wisconsin, United States of America; 2: Pohang University of Science and Technology, Korea, Republic of

Measurement and Modeling of the HTC Profile during Quenching of Hot Wall with a Falling Liquid Film

Tomio Okawa, Hiroyuki Umebayashi

The University of Electro-Communications, Japan

Optical Kerr Effect Gated Ultrafast Imaging of Bubbly Flows

Daniel Andrew Hunter, Philippe Matthieu Bardet

The George Washington University, United States of America

A Characterization of the Two-phase Frictional Pressure Drop within a Cylindrical Mini-channel in the Laminar and Turbulent Regimes

Jimmy Martin, Romuald Mallet, Yann Kervegant, Sylvain Chareyre

French Alternative Energies and Atomic Energy Commission (CEA), France

High-Resolution Miniaturized Impedance Sensor for Two-Phase Flow Measurement

Sergio Chiva, Oscar Prades, Guillem Monros, Salvador Torro, Raul Martinez, Jaume Luis

Universitat Jaume I, Spain

Measurement of Aerosol Temperature Field based on Background Oriented Schlieren

Bifan Liu, Danling Zhuang, Qian Wang, Junlian Yin

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

Validation of CATHARE Code Against PERICLES High Pressure Reflooding Experiments

Nicolas Piette, Raphaël Préa, Lopez Thibaut

CEA, France

On the Grid Resolution and Accuracy of under-resolved Direct Numerical Simulations Using the Spectral-element Method

Akshat Mathur¹, Shubham Dalvi¹, Mathis Bode², Ed Komen¹

1: NRG, Netherlands, The; 2: Forschungszentrum Jülich, Germany

Investigation on the Geometrical Representation of an Infinite Array of Rod Bundle Subchannels Using Direct Numerical Simulations (DNS)

Akshat Mathur¹, Jacob Ashwin Abraham², Marc Gerritsma², Ed Komen¹

1: NRG, Netherlands, The; 2: Delft University of Technology, Netherlands, The

A DNS Study on the Effect of Idealised Surface Roughness for Supercritical Flows Inhorizontal and Vertical Channels

Kenneth Chinembiri¹, Shuisheng He¹, Wei Wang²

1: University of Sheffield, United Kingdom; 2: Science and Technology Facilites Council, United Kingdom

High-fidelity CFD Simulation of a Turbulent Mixed Convection Axial Flow in a Heated Rod Bundle Using Code_saturne

Vladimir Duffal¹, Amine Laieb¹, Erwan Le Coupanec¹, Rodrigo Vicente Cruz², Cédric Flageul³, Eric Lamballais³, Stéphane Pujet¹, Sofiane Benhamadouche¹

1: EDF R&D, France; 2: CMCC Foundation - Euro-Mediterranean Center on Climate Change, Italy; 3: Pprime Institute, CNRS – Univ. Poitiers – ISAE/Ensma, France

Simulations of External Flow Around Twisted Elliptical Tubes for Above Unity Prandtl Numbers and Low to Moderate Reynolds Numbers

Sierra A Tutwiler¹, Dillon R Shaver², Lane B Carasik¹

1: Virginia Commonwealth University, United States of America; 2: Argonne National Laboratory, United Stated of America

The Implementation of the P1 Approximation in SpectralElement Code for Conjugate Heat Transfer

Haomin Yuan¹, Dezhi Dai¹, Dillon Shaver¹, Yu-hsiang Lan², Michael Seneca³, Tri Nguyen³, Elia Merzari³

1: Argonne National Laboratory, United States of America; 2: University of Illinois at Urbana-Champaign, United States of America; 3: Pennsylvania State University, United States of America

A Wall-Function Type Interface Turbulence Damping Method for Multiple Flow Regimes with Large Scale Interfaces

Vinesh H Gada, Mohit P Tandon

Siemens Industry Software, India

Implementing Improved Relative Velocity Models for Horizontal Bubbly Flow in Computational Multiphase Fluid Dynamics Simulations

Adam John Dix, Seungjin Kim

Purdue University, United States of America

Two-way Coupling Simulations of a Cantilever Rod under a Turbulent Axial Flow between a Beam Equation Solver and Wall-Resolved Large Eddy Simulation at a Moderate Reynolds Number

Thomas Norddine, Sofiane Benhamadouche

EDF R&D, France

Lattice Boltzmann Simulations of Natural Convection in Compressible Fluids

Junren Hou¹, Minyun Liu², Yugao Ma³, Yanping Huang², ShanFang Huang¹, Kan Wang¹

1: Tsinghua University, 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: Nuclear Power Institute of China, China, People's Republic of

Application of Apros and TRACE Codes for Turbine Trip and Inadvertent Operation of ECCS Transient Simulation of Small Modular Reactor

Matti Paananen¹, Tomi Pakarinen², Eerikki Raiko¹, Janne-Pekka Mäkinen²

1: Fortum Power and Heat Oy, Finland; 2: Platom Oy, Finland

Experimental Investigation of Flow Regimes and Friction Factor in a 9×9 Helical Cruciform Fuel Rod Bundle

Hansol Kim, Matthew Kinsky, Dalton Pyle, Joseph Seo, Yassin Hassan

Texas A&M University, United States of America

Analysis of Available Times during LOCA Sequences in NuScale Reactor Design Using the TRACE Code

Yago Martinez-Gonzalez¹, Cesar Queral¹, Kevin Fernandez-Cosials¹, Jorge Sanchez-Torrijos²

1: Universidad Politécnica de Madrid, Spain; 2: NFQ Advisory Services, Spain

Investigation of Multi-Dimensional Phenomena in Novel Passive Safety Systems for i-SMR Using MARS-KS

Jan Hruskovic¹, Sang Gyun Nam¹, Youngjae Park¹, Bub Dong Chung¹, Seong-Su Jeon¹, Seung-Jong Oh²

1: FNC Technology Co., Ltd., Korea, Republic of; 2: KEPCO International Nuclear Graduate School, Korea, Republic of

A Review of AP1000/AP600 Experimental Program and Its Applicability to AP300 SMR

Jun Liao, Megan Durse, Oriol Oliva, Richard Wright

Westinghouse Electric Company, United States of America

Uncertainty Quantification of a Postulated Severe Accident Scenario in a Generic German PWR

Livia Tiborcz, Thorsten Hollands

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany

ENSO Contribution to the HORIZON 2020 MUSA Project: In-Vessel Uncertainty Analysis with RELAP/SCDAPSIM/MOD3.4 and IUA2.0 of a Long-term SBO Scenario in a Gen-II PWR

Victor Martinez-Quiroga, Marina Perez-Ferragut

Energy Software Ltd., Spain

ENSO Contribution to the IAEA CRP I31033: Uncertainty Analysis with RELAP/SCDAPSIM/MOD3.5 of a Long-term SBO Scenario in a CAREM-like iPWR

Victor Martinez-Quiroga, Marina Perez-Ferragut

Energy Software Ltd., Spain

Stepwise Uncertainty Analysis Methodology in Severe Accidents

Rafael Bocanegra, Victor Martínez Quiroga, Marina Perez Ferragut

ENSO, Spain

Probability Analysis of Steam Generator Heat Transfer Tube Rupture under Severe Accident

ZhanXiang Huang

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

Acceleration of the Convergence of a Core Thermo-hydraulic Code Using Initialization from a Neural Network

Gauthier Lazare^1,2, Corentin Coudroy¹, Philippe Helluy², Erwan Le Coupanec¹, Qingqing Feng¹, Frank Hulsemann¹, Stéphane Pujet¹, Pauline Rotach¹

1: EDF, France; 2: IRMA, France

Model Calibration and Acceleration Techniques Based on Artificial Bee Colony Algorithm

Shubiao Dong, Xiaoyu Zhang, Qianping Zhang

China Nuclear Power Operation Technology Corporation, Ltd, China, People's Republic of

Thermal-Hydraulic Model Development for Semi-Circular Zigzag Channel PCHEs Based on Machine Learning

Shuai Che, Adam Burak, Xiaodong Sun

University of Michigan, United States of America

ANN-based Approach for Two-phase Model Development and Implementation in Thermal-hydraulic Codes

Van Thai Nguyen¹, Ngoc Dat Nguyen²

1: Hanoi University of Science and Technology, Vietnam; 2: Chungnam National University, Korea, Republic of

Thermal Stratification Prediction in Reactor System Based on CFD Simulations Accelerated by A Data-driven Coarse-grid Turbulence Model

Zijing Liu, Pengcheng Zhao, Yanan Zhao, Wei Deng, Tao Yu, Jinsen Xie

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

Towards a new NEA Framework for Advanced Thermalhydraulic Experiments for Nuclear Analysis and Safety Application (ATHENA)

Didier Jacquemain¹, Martina Adorni¹, Joelle Fleurot²

1: OECD NEA; 2: ASNR

Addressing Future Challenges on Analysis and Management of Accidents by International Cooperation: The Working Group on the Analysis and Management of Accidents (WGAMA)

Hideo Nakamura¹, Ahmed Bentaib², Martina Adorni³, Fulvio Mascari⁴, Pierre Ruyer⁵, Jinzhao Zhang⁶

1: Japan Atomic Energy Agency (JAEA), Japan; 2: Institut de Radioprotection et de Sureté Nucléaire (IRSN), France; 3: OECD Nuclear Energy (NEA); 4: National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Italy; 5: Autorité de sûreté nucléaire et de radioprotection (ASNR), France; 6: Tractebel (ENGIE), Belgium

NEA ETHARINUS Project: A Flagship Project Relevant to Thermal-Hydraulic Safety Analysis Issues

David Pialla¹, Joakim Holmstrom², Anis Bousbia Salah³, Martina Adorni⁴, Amina Younsi⁵, Sofia Carnevali⁶, Vesa Riikonen⁷, Simon Schollenberger⁸

1: EDF, France; 2: VATTENFALL-Ringhals AB, Sweden; 3: BEL V - Nuclear Safety and Analysis, Belgium; 4: OECD Nuclear Energy Agency, France; 5: ASNR, France; 6: Université Paris-Saclay, CEA, France; 7: LUT University, Finland; 8: Framatome, Germany

Key Outcomes of Recent NEA Nuclear Safety Joint Projects in Thermal-Hydraulics

Didier Jacquemain¹, Martina Adorni¹, Sangmin Lee¹, Markus Beilmann¹, Simon Philipp Shollenberger², Vesa Riikonen³, Jordi Freixa⁴, Kyoung-Ho Kang⁵, Miguel Sanchez Perea⁶, Sanjeev Gupta⁷, Martin Freitag⁷, Domenico Paladino⁸

1: OECD Nuclear Energy (NEA), France; 2: Framatome, Germany; 3: LUT University, Finland; 4: Universitat Politecnica de Catalunya, Spain; 5: Korea Atomic Energy Research Institute, Korea, Republic of; 6: Consejo de Seguridad Nuclear (CSN), Spain; 7: Becker Technologies GmbH, Germany; 8: PSI, Switwerland

Bal-Raj Sehgal Memorial Award Lecture: Interface Capturing Simulations for Nuclear Thermal Hydraulics

Igor Bolotnov

North Carolina State University, United States of America

Preventing Localized Hot Spots in Flow Boiling: CHF Enhancement Method for Non-Uniform Heat Conductance Surface

Nairamdakh Bold¹, Shuichiro Miwa¹, Shixian Wang¹, Koji Okamoto²

1: Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, Japan; 2: Nuclear Professional School, School of Engineering, The University of Tokyo, Japan

Effects of Oxidation on CHF on Bare and Grooved Copper Surface in Vertical-face Pool Boiling based on Bubble Behavior

Yanxu Huang¹, Zihao Wang¹, Kai Wang^1,2, Songbai Cheng³

1: Sun Yat-sen University, China, People's Republic of; 2: The University of Tokyo, Japan; 3: Harbin Engineering University, China, People's Republic of

Evaluating the Impact of Physical Models on Physics-Informed Machine Learning for Critical Heat Flux

Abdullah Al Mahmud^1,2, Asao Kanta¹, Koji Morita¹, Wei Liu¹

1: Kyushu University, Japan; 2: Bangladesh Atomic Energy Commission, Bangladesh

Dean Number Influence on CHF Occurrence in U-bend Tubes of Steam Generators

Tanuj Chauhan, Harish Pothukuchi

Indian Institute of Technology, India

Development of an Upgraded Critical Heat Flux Look-Up Table

Jun Yang, Aleksandar Vasić, Lanqin Yuan, Dé Groeneveld

Canadian Nuclear Laboratories, Canada

Numerical Study on Critical Heat Flux and the Influence of Eccentricity in Helical Cruciform Fuel under Non-Uniform Heating

Yuanjie Zhang¹, Bin Han¹, Xiaoliang Zhu¹, Baowen Yang²

1: Southeast University, China, People's Republic of; 2: DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, China, People's Republic of

Experimental Investigation on the Uncertainty of Three-sensor Conductivity Probe for Droplet Measurement

Kang Li^1,2, Wenxiong Zhou^1,2, Xubin Tan^1,2, Runzhi Huang^1,2, Mingyue He^1,2, Kexin Qu^1,2, Qiang Lian^1,2, Wan Sun^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

Preliminary Investigation of a Fiber Optic Technique for Flow Rate Measurement in Horizontal Air-Water Stratified Flow

Hanna Kim¹, Hyewon Lim², Hyungmo Kim¹

1: Mechanical Engineering, Gyeongsang National University, Korea, Republic of; 2: Graduate School of Mechanical and Aerospace Engineering, Gyeongsang National University, Korea, Republic of

Infrared Thermometry Investigation of Flow Boiling Transient Critical Heat Flux under Exponentially Escalating Heat Input on Surfaces with Different Finish and Wettability

Yang Liu, Sebastian Rodriguez Rosero, Florian Chavagnat, Matteo Bucci

Massachusetts Institute of Technology, United States of America

Borescopic Molecular Tagging Velocimetry in PWR Surrogate Bundle

Roberto Capanna¹, Charles Fort¹, Guillaume Ricciardi², Philippe Bardet¹

1: The George Washington University, United States of America; 2: CEA, DES, IRESNE, Nuclear Technology Departement, France

CFD-Grade Measurements of Flow-Debris Interaction and PWR Filter Clogging Behavior using MRI Scanner

Vincent Klempau¹, Markus Rehm², Kristine John¹, Elmar Rieder², Sven Grundmann¹, Martin Bruschewski¹

1: University of Rostock, Germany; 2: Framatome GmbH, Germany

Challenges and Non-Conservatism in Indirect Simulation Heaters for Thermal-Hydraulic Experiments

Bao-Wen Yang¹, Jeremy Silber¹, Eric Yang², Stephanie H. Yang¹, Ray Smith², Yash Yadav², Bin Han³

1: Delta Energy Group New York (DEGNY/GDES), United States of America; 2: CARP Associates USA, LLC, United States of America; 3: Southeast University, China, People's Republic of

Solidification-Melting Behaviors and Mushy Characteristics of Molten Salt in Filling Horizontal Cold Pipe

HongXiang Yu^1,2, Chong Zhou^1,2, Xiaofeng Yuan¹, Yushuang Chen^1,2, Shanwu Wang¹, Hui Deng^1,2

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

Optimizing Core Stability and Flow in Passive Molten Salt Fast Reactors Using GeN-Foam

Juhyeong Lee¹, Do won Lee¹, Yonghee Kim², Sangtae Kim¹, Sung Joong Kim¹

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

Thermal-hydraulic Research Progress in Fluoride Salt Cooled Nuclear Reactor Applied in Commercial Ship

Limin Liu, Jiaming Zhang, Hanyang Gu

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

A Coupled OpenFOAM-Modelica Modelling Framework for Analysing MSR Safety-Related Transients

Sophie Deanesi, Stefano Lorenzi

Politecnico di Milano, Italy

Enhanced Multi-Physics Modelling of the MSRE Using GeN-Foam

Shervineh Amirkhosravi¹, Frik van Niekerk¹, Marina du Toit¹, Alessandro Scolaro², Andreas Pautz²

1: North-West University, South Africa; 2: EPFL, Switzerland

Implementation of Molten Salt – Concrete Interactions into a System Thermal-Hydraulic Code SPECTRA

Marek Stempniewicz, Ferry Roelofs, Eric de Geus

NRG, Netherlands, The

Development of a Boiling Model at Bubble Scale

Marine Amoros, Ferdinand Louis, Nicolas Goreaud, Alejandro Carlos Mourgues Codern

FRAMATOME SAS, France

Numerical Modeling Saturated Pool Boiling Condition with Ultrasonic Treatment

Luyao Tang, Mingchen Gao, Wei Xu, Xiaojing Liu

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

Vortex and Turbulence Statistics in Nucleate Pool Boiling

Sara Youssoufi¹, Amir Riaz², Elias Balaras¹

1: George Washington University, United States of America; 2: University of Maryland, United States of America

Development of an Advanced Wall Boiling Model to Predict Dryout in CANDU Flow Conditions

Robert Brewster¹, Emilio Baglietto¹, Krishna Podila², Geoff Waddington²

1: Massachusetts Institute of Technology, United States of America; 2: Canadian Nuclear Laboratories, Canada

Interface Capturing Simulation of Subcooled Turbulent Flow Boiling

Nicholas J. Mecham, Nam T. Dinh, Igor A. Bolotnov

North Carolina State University, United States of America

Turbulent Free Convection in a Pool Combining Bubble Dynamics, Surface Evaporation and Water Level Descent

Joauma Marichal¹, Pierre Ruyer², Yann Bartosiewicz¹

1: Université Catholique de Louvain, Belgium; 2: Autorité de Sûreté Nucléaire et de Radioprotection (ASNR), France

Numerical Prediction of Two-Phase Flow in Tube Bundles with the 3D Mixture Multiphase Model

Hamza Ahfidi, Nicolas Goreaud, Ferdinand Louis

Framatome SAS, France

OpenSTREAM: An Open-Source Platform for Two-Phase Flow Modeling and Simulation

Jean-Marie Le Corre¹, Jason Chan², Elisabeth Walter³, Evan T. Hurlburt⁴, Roman W. Morse⁵

1: Westinghouse Electric Sweden AB, Sweden; 2: University of Wisconsin-Madison, United States of America; 3: Royal Institute of Technology, Sweden; 4: Naval Nuclear Laboratory, United States of America; 5: Massachusetts Institute of Technology, United States of America

Development of Validation Technology for Detailed Two-Phase Flow Simulation Codes for Innovative Reactor Design

Hiroyuki Yoshida, Naoki Horiguchi, Ayako Ono

Japan Atomie Energy Agency, Japan

Study of Two-Phase Void Fraction in a Rectangular Channel Using Capacitance Sensor

Peterson Ngoc Nguyen, Kazuya Tajiri

Michigan Technological University, United States of America

CFD Analysis of Diffuser Configurations for Enhanced Oxygen Transfer and Flow Mixing in Two-Phase Reactor Systems

Sergio Chiva, Jaume Luis, Raul Martinez-cuenca, Oscar Prades, Guillem Monros, Salvador Torro

Universitat Jaume I, Spain

A Closure Model for Local Vapor Bubble Nucleation and Waiting Time

Aaron Lentner, Sara Youssoufi, Elias Balaras

George Washington University, United States of America

R&D Acitivities of the GIF Safety and Operation Project of Sodium-cooled Fast Reactor Systems

Jewhan Lee¹, Acacia Brunett², Fabienne Delage³, Hidemasa Yamano⁴, Jin Wang⁵, Pierre Sciora^3,6

1: KAERI, Korea, Republic of; 2: ANL, United States of America; 3: CEA, France; 4: JAEA, Japan; 5: CIAE, China, People's Republic of; 6: EURATOM, Europe

Validation of Subchannel Code CTF for Sodium Fast Reactor Modelling

Jonas Vanderwaeren¹, Lucia Rueda Villegas¹, Christophe Schneidesch¹, Elias-Yammir Garcia-Cervantes²

1: TRACTEBEL, Belgium; 2: CEA, France

Analysis of Cliff Effects and Thermal Hydraulic Instabilities in the PLANDTL-2 Sodium Experiment Transient Tests

Sébastien Renaudière de Vaux¹, Simon Li¹, Toshiki Ezure², Masaaki Tanaka²

1: CEA, France; 2: JAEA, Japan

Core Deformation Reactivity with Neutronics-Thermal Hydraulics-Structural Mechanics Coupled Analysis for FFTF LOFWOS Test #13

Norihiro Doda¹, Shinya Kato¹, Tomoyuki Uwaba¹, Yoshiaki Nakamine², Kennichi Igawa³, Masaki Iida³, Masaaki Tanaka¹

1: Japan Atomic Energy Agency, Japan; 2: NDD Corporation, Japan; 3: NESI Inc., Japan

Visualization of Sudden Gas Release Replicating Fuel Pin Failure in LMFR Geometry

Nicholas Gallagher¹, Guillaume Mignot¹, Wade Marcum¹, Aydin Karahan², Samuel Miller³

1: Oregon State University, United States of America; 2: Argonne National Laboratory, United States of America; 3: TerraPower LLC, United States of America

Development of Physical Models to Simulate Disrupted Core in Metal-fuel Sodium-cooled Fast Reactors

Hirotaka Tagami, Yasushi Okano, Hidemasa Yamano

Japan Atomic Energy Agency, Japan

Fuel Coolant Interaction/Ex- vessel Steam Explosion: An Overview of Experimental Tests Performed at CEA with Prototypic Corium in the Frame of ICE Program

Pascal Piluso¹, Jules Delacroix¹, Andrea Quaini¹, Emmanuelle Bracks¹, René Guinebretière², Denis Menut³, Renaud Meignen⁴, Nicolas Rimbert⁵

1: CEA, France; 2: University of Limoges, France; 3: Synchrotron SOLEIL, France; 4: ASNR, France; 5: University of Lorraine, France

Impact of Advanced Technology Fuel Cladding Materials on the Progression of Severe Accidents in a Generic Natural-Circulation iPWR

Mauricio Exequiel Cazado¹, Zaira Itzel Jimenez Balbuena¹, Laure Carénini², Fabrizio Gabrielli¹, Victor Hugo Sánchez-Espinoza¹

1: Karlsruhe Institute of Technology (KIT), Germany; 2: French Authority for Nuclear Safety and Radiation Protection (ASNR), France

Mitigation of Radioactive Release during Underwater Laser-cutting of Corium after a Severe Accident: An Analytical Study

Luis Herranz¹, Rafael Iglesias¹, Emmanuel Porcheron²

1: CIEMAT, Spain; 2: ASNR, France

Investigation of the Effects of Surface Inclination on the Ablation of a Solid by the Impact of Hot Liquid Jet: Implications for Sodium-cooled Fast Reactor Safety

Asma Djermoune^1,2, Alexandre Lecoanet¹, Nathalie Seiler¹, Nicolas Rimbert², Michel Gradeck²

1: CEA, France; 2: Université de Lorraine, France

Development and Qualification of Advanced Core Catcher for SFR

Prabhat Kumar Shukla^1,2, E. Hemanth Rao¹, Anish Kumar^1,2, Sagar Nagpure¹, G. Muthu Kumar¹, Avinash Kumar Acharya¹, Sanjay Kumar Das¹, B.K Sreedhar¹

1: Indira Gandhi Centre for Atomic Research, India; 2: Homi Bhabha National Institute, India

Quantification of the Influence of Air Entrainment on Triggering of Single Molten Droplet

Cheng Peng¹, Kaiwen Shi¹, Dong Li¹, Dmitry Grishchenko², Pavel Kudinov²

1: Shanghai University of Electric Power, China, People's Republic of; 2: Royal Institute of Technology, Sweden

Flashing Induced Instabilities in a Forced Circulation Loop under Low Pressure and Low Power Conditions

Karim Mohammed Abdalwaged Yassin, Carlos Alberto Dorao, Maria Fernandino

Norwegian university of Science and Technology (NTNU), Norway

Theoretical Analysis of Two-Phase Flow Instability in Once-through Steam Generator Using Drift Flow Model

Yang Su, Xiaowei Li, Hongyi Fan, Xinxin Wu, Xiaowei Luo

Tsinghua University, China, People's Republic of

Theoretical Model of Water Jet Instability and Phase Change Steam Expansion during SGTR in Lead-cooled Fast Reactor

Ruiqi Bao, Li Liu, Hanyang Gu

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

The Study of Transient Heat Transfer Mechanisms and Two-Phase Flow during Post Flow Instability Dryout Accident

Yosef Aharon¹, Almog Chakmon^1,2, Gennady Ziskind²

1: NRCN, Israel; 2: Ben Gurion University, Israel

Defining Axial Void Fraction and Flashing Details from Pressure Profiles in Two-phase Critical Flow Discharges Made in CRAFTY Facility

Lauri Pyy, Giteshkumar Patel, Silja Oksanen, Juhani Hyvärinen

LUT University, Finland

A Study on the Phase State Measurement Method for Gas-liquid Two-phase Flow in a Tube during SCO₂ Loss-of-pressure Flash Vaporization

Junjie Yuan, Li Liu, Hanyang Gu

Shanghai Jiaotong University, China, People's Republic of

Sodium Heat Pipe under Pulsed Power near Operation Limits

Pablo Diaz Gomez Maqueo, Reilly MacCoy, Rory McGrath, Chukwudi Azih

Canadian Nuclear Laboratories, Canada

Development of a High-Temperature Heat Pipe Simulation Module for the Thermal Hydraulic System Code AC²/ATHLET: Laminar Vapor Flow Modeling

Daniel Eckert¹, Philipp Schöffel¹, Fabian Weyermann¹, Andreas Schaffrath¹, Jörg Starflinger²

1: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany; 2: Institute of Nuclear Technology and Energy Systems (IKE), University of Stuttgart, Germany

Parametric Optimization of Heat Pipe Design for Enhanced Thermal Performance Using Genetic Algorithm

Linjie Xu, Panhe Ge, Gu Hu

China Institute of Atomic Energy, China, People's Republic of

A Flexible Coupling Approach for Heat Pipe Microreactor Analysis

Mario A. Ponce Tovar^1,2, Cynthia Camila Güttlein^1,3, Ivor David Clifford¹, Alexey Cherezov¹, Hakim Ferroukhi¹

1: Paul Scherrer Institut, Switzerland; 2: Eidgenössische Technische Hochschule Zürich (ETH Zurich), Switzerland; 3: École Polytechnique Fédérale de Lausanne (EPFL), Switzerland

Neutronics and Planned Coupled Neutronics-Thermal hydraulics Simulations of a Heat Pipe Cooled MMR Core

Norman Dünne¹, Jeremy Bousquet¹, Andreas Wielenberg¹, Andreas Schaffrath¹, Jörg Starflinger²

1: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Germany; 2: University of Stuttgart, Germany

Design Study to Develop an Experimental Facility for a Microreactor Process Heat Application: Cement Calcination

Scout Bucks¹, Ama Dahanayake¹, Erik Hisahara¹, Martin Nieto-Perez¹, Saya Lee¹, Sola Talabi², Sathish Krishnamoorthy³

1: The Pennsylvania State Univeristy, United States of America; 2: Pittsburgh Technical, United States of America; 3: Nazareth Cement Plant, Heidelberg Materials US Inc., United States of America

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

FONESYS Benchmark of Core Interfacial Friction Models in System Codes

Dominique Bestion¹, Francesco D'Auria², Qingling Cai², Jaeseok Heo³, Philipp Schoeffel⁴, Hongsheng Yuan⁵, Amandine Capogna⁶, Sofia Carnevali⁶

1: Consultant, France; 2: UNIPI, Italy; 3: KAERI, Korea, Republic of; 4: GRS, Germany; 5: CNPRI, China, People's Republic of; 6: CEA, France

Giving a Major Role to Bifurcating Events in Pirt and Scaling Analysis for Light Water Reactor Thermalhydraulics

Dominique Bestion¹, Sofia Carnevali², Francesco D'Auria³

1: Consultant, France; 2: CEA, France; 3: UNIPI, Italy

Current and Planned Activities of the FONESYS Network of System Code Developers in Collaboration with the SILENCE Network of Experimentalists

Dominique Bestion¹, Francesco D'Auria², Klaus Umminger³, Jaeseok Heo⁴, Philipp Schoeffel⁵, Sofia Carnevali⁶, Jean Luc Vacher⁷, Pierre Gaillard⁸, Huie Sha⁹, Hongsheng Yuan¹⁰, Geoffrey Waddington¹¹, Jean Marie LeCorre¹²

1: Consultant, France; 2: University of Pisa, Italy; 3: Consultant, Germany; 4: KAERI, Korea, Republic of; 5: GRS, Germany; 6: CEA, France; 7: EDF, France; 8: Framatome, France; 9: SPICRI, China, People's Republic of; 10: CNPRI, China, People's Republic of; 11: CNL, Canada; 12: Westinghouse, Sweden

FONESYS Benchmark of Core-3D-Mixing in System Codes

Dominique Bestion¹, Jaeseok Heo², Huie Sha³, Philipp Schoeffel⁴, Adrien Rodriguez⁵, Hongsheng Yuan⁶, Vincenzo Zingales⁷, Raphael Prea⁵, Lin Wang³, Francesco D'Auria⁷

1: Consultant, Grance; 2: KAERI, Korea, Republic of; 3: SPICRI, China, People's Republic of; 4: GRS, Gernany; 5: CEA, France; 6: CNPRI, China, People's Republic of; 7: UNIPI, Italy

Fonesys Benchmark of Singular Pressure Losses in System Codes

Dominique Bestion¹, Philipp Schoeffel², Nicolas Piette³, Jean Luc Vacher⁴, Jae Jun Jeong⁵, Qingling Cai⁶, Vincenzo Zingales⁶, Jaeseok Heo⁷, Francesco D'Auria⁶

1: Consultant, France; 2: GRS, Germany; 3: CEA, France; 4: EDF, France; 5: Pusan National University, Korea, Republic of; 6: UNIPI-GRNSPG, Italy; 7: KAERI, Korea, Republic of

Using System Code for Scaling Analysis: A New Integrated Tool in the CATHARE Code Applied to a SB-LOCA Transient

Valentin Cottarel¹, Sofia Carnevali¹, Marco Montanini¹, Dominique Bestion²

1: French Alternative Energies and Atomic Energy Commission (CEA), France; 2: Scientific Consultant, France

The CATHARE Code Validation on CRIEPI Core Void Fraction Data

Amandine Capogna¹, Jean-Luc Vacher², Thibaut Lopez¹, Dominique Bestion³

1: CEA, France; 2: EDF, France; 3: Consultant, France

Impact of Electroplated Porous Copper Layer Thickness on Critical Heat Flux in Saturated Pool Boiling

Yuya Hayashida¹, Yutaro Umehara^1,2, Atsuro Etoh¹, Shoji Mori^1,2

1: Kyushu University, Japan; 2: International Institute for Carbon-Neutral Energy Research, Japan

Numerical Study on Critical Heat Flux and the Influence of Eccentricity in Annular Pipe under Non-Uniform Heating

Bin Han¹, Yuanjie Zhang¹, Xiaoliang Zhu¹, Baowen Yang²

1: Southeast University, China, People's Republic of; 2: DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, China, People's Republic of

Preliminary Pool Boiling Experimental Study on the Impact of Deposition on the Critical Heat Flux of Horizontally Placed Tubes

Xiaowen Wang¹, Maolong Liu², Tenlong Cong¹, Yao Xiao¹, Hanyang Gu¹

1: Shanghai Jiaotong University, China, People's Republic of; 2: Fudan University, China, People's Republic of

Exploring a Link between Void Fraction Profile and Critical Heat Flux in Subcooled Flow Nucleate Boiling

Sebastian Rodriguez Rosero, Alexander Edwards, Matthew Hughes, Florian Chavagnat, Matteo Bucci

Massachusetts Institute of Technology, United States of America

CHF Experiments for Pool Boiling from Inclined Heater Surfaces with Stainless Steel 304 Plates

Young Hee Kim¹, Dong Hun Shin¹, Min Suk Lee², Dong Hoon Kam³, Yong Hoon Jeong¹

1: Korea Advanced Institute of Science and Technology, Korea, Republic of; 2: Texas A&M University, United States of America; 3: Argonne National Laboratory, United States of America

Assessment of Heat Flux Partitioning Approaches for the Prediction of Boiling and the Critical Heat Flux

Omid Bidar, Marco Colombo

University of Sheffield, United Kingdom

Experimental Design and Algorithm Validation of Reactor Chemical and Volume Control System Upper Charging Line Valve Leakage Faults

Jiajun Li, Hengyuan Wei, Dongyang Li, Sichao Tan, Ruifeng Tian

Harbin Engineering University, China, People's Republic of

Basic Design of PCCS Heat Exchanger of Integral Effect Test Facility for i-SMR Validation Test

Jin-Hwa Yang, Byoung-Uhn Bae, Hwang Bae, Kyoung-Ho Kang

Korea Atomic Energy Research Institute, Korea, Republic of

The Improvement and Preliminary Validation of Relap5 Code for Integrated Natural Circulation SMR

Zhanfei QI, Xiumei Zhao, Zijiang Yang, Shengzhe Li, Yue Wu

SNERDI, China, People's Republic of

Integrated Thermo-Mechanics and Thermal-Hydraulics of Zircaloy-4 Cladding Behavior under LBLOCA Conditions Using the ICARUS Facility

Rahmatika Intan Ali^1,2, Jongrok Kim¹, Kihwan Kim¹, Sang-Ki Moon¹, Seok Kim¹, Jae Bong Lee^1,2

1: Korea Atomic Energy Research Institute, Korea, Republic of; 2: KAERI School, University of Science and Technology, Korea, Republic of

A Scaled-Down Approach for Designing a Compact Hydraulic Apparatus for Nuclear Experimental Liquid fuel reactors (CHANEL)

Hyeon Ji Kim, In Cheol Bang

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

Experimental Investigations of Natural Convection in a Differentially-Heated Cavity

Noah LeFrancois, Robert Bowden

Canadian Nuclear Laboratories, Canada

Undercooling Conditions in SFR Low Void Core Designs

Sara Perez-Martin

Karlsruhe Institute of Technology, Germany

Development of a Novel OpenFOAM Solver for Tritium Permeation Modeling in Molten Fluoride Salt Systems

Wooseong Park^1,2, Guanyu Su¹, Yong Hoon Jeong²

1: UC Berkeley, United States of America; 2: KAIST, Korea, Republic of

CFD Simulation of Geyser Boiling and Startup Instabilities of a Two-Phase Closed Water Thermosyphon using OpenFOAM

Almanzo Arjuna, In Cheol Bang

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

CFD Modeling of Thermal-hydraulic Behavior in SCWR: Analysis of Trans-critical Transients

Shubham Rajesh Vaidya, Goutam Dutta, Harish Pothukuchi

Indian Institute of Technology Jammu, India

Modelling of Selected SAFARI-1 Research Reactor Transients using RELAP/SCDAPSIM/MOD3.4

Samukeliswe Nozipho Khoza, Rian Hendrik Prinsloo

South African Nuclear Energy Corporation SOC Limited (Necsa), South Africa

Experimental Study of Mass Transfer and Solubility of Boric Acid with Steam

Zehua Zhao¹, Guogang Bao², Lili Tong¹, Xuewu Cao¹

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

Flow Analysis in a 3×3 Helical Cruciform Fuel Bundle Using Magnetic Resonance Velocimetry for CFD Validation

Hyeongi Moon, Sejin Oh, Hangfei Dong, Simon Song, Minseop Song

Hanyang University, Korea, Republic of

Flow Structure and Temperature Fluctuation of Penetration Flow in a T-junction Branch Pipe with an Upstream Elbow

Koji Miyoshi

Institute of Nuclear Safety System, Inc., Japan

Multi-hour Steam Generator Transient Temperature Modelling for Stress Analysis Using Conjugate Heat Transfer CFD

Graham Macpherson¹, Chris Sigournay²

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

Study on the Effect of the Dissolved Gas in the Hydroaccumulator

Attila Guba, Aron Hegedus

HUN-REN Centre for Energy Research, Institute for Atomic Energy Research, Hungary

FeCrAl and Cr Coating ATF Performance in Accidental Sequences of VVER-1000 Reactors

Elena Redondo-Valero¹, Jorge Sanchez-Torrijos¹, Cesar Queral², David Canal², Emilio Castro-Gonzalez², Kevin Fernandez-Cosials², Victor Sanchez-Espinoza³

1: NFQ Advisory Services, Spain; 2: Universidad Politécnica de Madrid, Spain; 3: Karlsruhe Institute of Technology (KIT), Germany

A Broyden-Type Newton Method for Two-Fluid Model’s Fully-Implicit Solution Scheme

Hao Zhang, Meng Zhao, Yanhua Yang

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

Simulation of BWR-Relevant Swirling Annular Flow Using the Conservative Level Set Method

Taylor Edwin Grubbs, Nicholas Mecham, Igor Bolotnov

North Carolina State University, United States of America

Assessment of Drag Force Formulations for Two-field All-flow-regime Models

Peio Berrécochéa Machingoréna^1,2, Dominique Legendre², Daniele Vivaldi¹

1: ASNR (Autorité de Sûreté Nucléaire et de Radioprotection), France; 2: IMFT (Institut de Mécanique des Fluides de Toulouse), France

Investigation on Bubble Residence Time of Swarm Flow in Pool Scrubbing Process

Fanli Kong, Xing Chen, Xu Cheng

Karlsruhe Institute of Technology, Germany

Numerical Investigation on the Structural Integrity of an Ex-vessel Core Catcher under Guillotine-type RPV Failure Using Smoothed Particle Hydrodynamics

Jin-Woo Kim¹, Hee Sang Yoo^1,2, Tae Hoon Lee¹, Yelyn Ahn¹, Min Chan Kwon¹, Eung Soo Kim¹

1: Seoul National University, Korea, Republic of; 2: French Alternative Energies and Atomic Energy Commission (CEA), France

Analysis of Corium Stratification Effect on Molten Core-Concrete Interaction observed in the MOCKA 3.1 Test

Jun Sung Choi, Tae Hwan Kim, Jin-Woo Kim, Min Jae Kim, Eung Soo Kim, Hyun Sun Park

Seoul National University, Korea, Republic of

Development of the New Jet Breakup Length Correlation Considering the Effect of Vapor Generation Intensity on the Melt Jet Fragmentation

WooHyun Jung¹, Hyun Sun Park²

1: University of Wisconsin, United States of America; 2: Seoul National University, Korea, Republic of

Empirical Feedback on Layout Design Optimization of Reactor Cavity Water Injection Cooling System

Li Peng, Zhe Jiang

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

URANS Simulation of CANDU Debris Bed Transient Melting in a Severe Accident

Yeshan Sun, Stephen Tullis, Marilyn Lightstone

McMaster University, Canada

Hydrogen Concentration Distribution in the Reactor Building of Fukushima Daiichi NPP Unit-3

Masanori Naitoh, Fumitomo Onishi, Atsuo Takahashi, Toshoharu Mitsuhashi, Achihoro Hamano, Hirotaka Hadachi

Advancesoft Corporation, Japan

Test Results of an HTSE Experimental Facility Integrating with a Helium Loop for Low Carbon Hydrogen Production

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

Korea Atomic Energy Research Institute, Korea, Republic of

NuScale Integrated Energy System for Petrochemical Plant Emissions Reduction

Jose Reyes, Luis DePavia, John Swanson

NuScale Power, United States of America

Performance Analysis of the Nuclear-powered IECT Propulsion System

Hangqian Liu^1,2, Ao Zhang¹, Xiang Wang*¹

1: Harbin Engineering University, China, People's Republic of; 2: University of Science and Technology of China, China, People's Republic of

Multi-objective Decisions on Integrated Energy Systems Planning and Operation for Industrial Combined Heat and Power Supply

So-Bin Cho^1,2, Junyung Kim¹, Václav Novotný¹, Rami M. Saeed¹, Todd Allen², Xiaodong Sun²

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

A Realistic Metric for Latent Heat Thermal Energy Storage Systems to be Paired with Advanced Reactors

Beau Walsh, Guanyu Su

UC Berkeley, United States of America

S-Allegro Integral Test Facility Thermal Hydraulic Benchmark: Steady State Qualification of Heat Exchanger Models

Boris Kvizda¹, Miriama Lacková¹, Slavomír Bebjak¹, Bendegúz Kopp², Tamás Varju², Zalán Csekei³, Zsombor Bali³, Gusztáv Mayer³, Tomas Melichar⁴, Daniel Kříž⁴, Jedrzej Walkowiak⁵, Michal Spirzewski⁵

1: VUJE, a.s., Slovak Republic; 2: Budapest University of Technology and Economics, Hungary; 3: HUN-REN Centre for Energy Research, Hungary; 4: Centrum Vyzkumu Rez, s.r.o., Czech Republic; 5: Narodowe Centrum Badan Jadrowych, Poland

Thermal-hydraulics Analysis of ALLEGRO Gas-cooled Fast Reactor with Improved Refractory Core

Gusztáv Mayer¹, Zsombor Bali^1,2, Attila Guba¹

1: HUN-REN Centre for Energy Research, Institue for Atomic Energy Research, Hungary; 2: Budapest University of Technology and Economics, Hungary

Preliminary Validation of Radiation Model Comparison for Radiative Heat Transfer Analysis in MHTGR RCCS

Je-Hyeong Park, Jae-Ho Jeong

Chung-Ang University, Korea, Republic of

Research on the Development of Simulation Models for Stirling Integrated Gas-Cooled Reactors

Tao Zhou¹, Shuaijie Lu², Genglei Xia¹, Yuandong Zhang¹, Guanghui Jiao¹

1: Harbin Engineering University, China, People's Republic of; 2: Wuhan Second Ship Design and Research Institute, China, People's Republic of

Modelling of the S-ALLEGRO Secondary Heat Exchanger in ATHLET

Zsombor Bali^1,2, Attila Guba¹, Gusztáv Mayer¹

1: HUN-REN Centre for Energy Research, Institute for Atomic Energy Research, Hungary; 2: Budapest University of Technology and Economics, Hungary

Analysis of ATWS Scenarios in HTR-10 Operating at Higher Temperatures

Yanhua Zheng¹, Marek Stempniewicz², Xin Wang¹, Ferry Roelofs², Sun Jun¹

1: INET, Tsinghua University, China, People's Republic of; 2: Nuclear Research Group, Netherlands, The

Experimental Investigation of a Compact Diffusion-Bonded Steam Generator for High-Temperature Gas Reactors

Ji Yong Kim¹, Haekyun Park^1,2, Xiaodong Sun¹

1: University of Michigan, United States of America; 2: Kyungpook National University, Korea, Republic of

Experimental Validation of Identified Dimensionless Pitch Parameter of Additively Manufactured Helically Rifled Tubing for Molten Salt Heat Exchangers

Ryan Patrick McGuire, Lane Carasik, Andrew Hutsell, James Vulcanoff, Sierra Tutwiler

Virginia Commonwealth University, United States of America

Experiments on Thermal Stratification at Horizontally Oriented Pipeline-Elbows

Zhongkang Ma, Mi Zhou, Naiqiang Zhang

North China Electric Power University, China, People's Republic of

Flow Pattern Transition and Separation Performance of Swirl-Vane Separator in Small Modular Reactors

Luyun Mao, Nan Gui

Tsinghua University, China, People's Republic of

Comparison of MARS-KS and SPACE Code for Simulating a Helical Steam Generator Two-phase Instability

Junha Hwang, Seunghwan Oh, Jeong Ik Lee, Doh Hyeon Kim, Semin Joo, Taeyeon Min

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

Experimental and Numerical Investigation on the Resistance Characteristics of the New Throttling Device for Steam Generators

Bo Wang^1,2, Yukang Liu¹, Yin Fang², Xianliang Lei², Yanfang Liu¹, Runze Liu², Xinyang Guo²

1: Dongfang Electric Co.Ltd., China, People's Republic of; 2: Xi’an Jiaotong University, China, People's Republic of

Study of Reactor Core Residual Heat Removal Schematic

Jiaming Zhao, Rui Zhang, Xiaoxia Chen, Nianzhe Zhang, Xiangyu Chi

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

Verification of the Reflectivity of the Boundary Surface Regarding the Development of Water Level Measurement Technology Using Ultrasound

Takahiro Ito¹, Kohei Kikuchi¹, Weichen Zhang¹, Hiroshige Kikura¹, Daisuke Sasa², Takeshi Suzuki²

1: Laboratory for Zero-Carbon Energy, Institute of Science Tokyo, Japan; 2: Tokyo Electric Power Company Holdings, Inc., Japan