Conference Agenda

Shaping the Future of Nuclear Energy: Thermal Hydraulics, Key to Robust Defense-in-Depth and Severe Accident Management

Véronique Rouyer

OECD Nuclear Energy Agency, France

Thermal Hydraulics Innovation Enables Global Nuclear Energy Resurgence

W. David Pointer

Oak Ridge National Laboratory, United States of America

Regulation and Research for Demonstrating and Deploying Advanced Nuclear Systems

Toyoshi Fuketa

Nuclear Damage Compensation and Decommissioning Facilitation Corporation, Japan

From Models to Agents: Rethinking Safety Analysis in the Age of AI

Nam Dinh

North Carolina State University, United States of America

Artificial Intelligence and Nuclear Power: Developments and Challenges

Kyun-Tae Kim

Korea Institute of Nuclear Safety, Korea, Republic of

Advancing LWR Core Thermal Hydraulics Through Disruptive Innovation

Jean-Marie Le Corre

Westinghouse Electric Company, Sweden

Identification of Boiling Regime Based on Hydrodynamic Behavior and Heat Transfer Characteristics of Single Droplet-Heated Wall Collision

Ahyeong Cho, Hyungdae Kim

Kyung Hee University, Korea, Republic of

Modeling of Distribution Parameter and Drift Velocity for Microgravity Two-phase Flow

Xu Han^1,2, Aijie Li^1,2, Shixun He^1,2, Xiaobo Zeng^1,2, Di Wu^1,2, Jie Cheng^1,2, Jianjun Wang^1,2

1: College of Nuclear Science and Technology, Harbin Engineering University, China, People's Republic of; 2: Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment, Harbin Engineering University, China, People's Republic of

Geometric Effects of Inverted U-bend on Two-phase Transport

Zhengting Quan, Alicja Stoppel, Seungjin Kim

Purdue University, United States of America

A Simulant of R134a-Ethanol Flow for Investigating Steam-water Annular Flow under High-pressure and High-temperature Conditions

Huacheng Zhang¹, Yutaro Umehara¹, Shoji Mori¹, Naoki Horiguchi², Hiroyuki Yoshida²

1: Kyushu University, Japan; 2: Japan Atomic Energy Agency, Japan

One-group Interfacial Area Transport in Vertical Two-phase Flow with Inverted U-bend

Zhengting Quan, Seungjin Kim

Purdue University, United States of America

Mechanistic Model of Heat Transfer Coefficient in AnnularTwo-Phase Flow

Roman W. Morse¹, Gustavo Aguiar¹, Kristofer M. Dressler², Jean-Marie Le Corre³, Evan T. Hurlburt⁴, Matteo Bucci¹

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

CFD Analysis of the Thermal-hydraulic Behavior during Loss of Coolant Accident (LOCA) Using ATLS-CUBE Test Facility Results

Mubashir Hassan¹, Nourah Alyammahi², Yacine Addad¹

1: Khalifa University of Science and Technology, United Arab Emirate; 2: Federal Authority for Nuclear Regulation (FANR), United Arab Emirate

RELAP5 and TRACE Simulations of Reflood Experiments at the RBHT Facility

Luís De Juan, Jordi Freixa

Universitat Politècnica de Catalunya, Spain

Modelling and Validation of Mixed Convection Flows in the SUPERCAVNA Facility using CFD Tools

Clotaire Geffray, Alain Genty

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

Investigating TRACE Thermal Hydraulics Code through Sensitivity Analysis and Inverse Uncertainty Quantification: A Case Study at KAIST's Condensation Test Facility

Samah A. Albdour, Yacine Addad

Khalifa University, United Arab Emirates

High-detailed CFD-Investigation of the MOTEL Facility for the Analysis of Cross-flow Experiments

Michael Böttcher, Victor Sanchez-Espinosa

Karlsruhe Institute of Technology, Germany

Investigation of Bolgiano-Obukhov Scaling in Mixed Convective Flow with a LES Model of the GaTE Facility

Theodore Ming-Rei Chu, Lane B. Carasik

Virginia Commonwealth University, United States of America

An Overview of Ongoing and Planned R&D Activities in the Field of Experimental Two-phase Thermal-hydraulics at CEA IRESNE

Jimmy Martin, Philippe Aubert, Stéphane Bantiche, Manon Bottin, Jérôme Brinster, Florence Bruna, Julien Carré, Sidonie Clément, Christine Coquelet-Pascal, Jean-Philippe Descamps, Fabrice François, Sébastien François, David Guénadou, Anthony Laurent, Matthieu Manzoni, Bastien Menc, Damien Moulin, Rémy Savoyet, Ludovic Sou, Mathilde Talluau, Eric Verloo

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

Experiment Investigation of Condensation Effect on an Integral Facility

Zijiang Yang, Di Liu, Zhanfei Qi, Kemei Cao

Shanghai Nuclear Engineering and Design Corporation, China, People's Republic of

Validation on Condensation Heat Transfer Models of SPACE and MARS-KS based on Condensation Experiment Facility for Small Modular Reactor Passive Safety System

Hyo Jun An¹, Jae Hyung Park¹, Taeseok Kim², Geunyoung Byeon¹, Yujin Kim¹, JinHo Song¹, Sung Joong Kim^1,3

1: Department of Nuclear Engineering, Hanyang University, Korea, Republic of; 2: Jeju National University, Korea, Republic of; 3: Institute of Nano Science and Technology, Hanyang University, Korea, Republic of

Erosion of a Stratified Containment Atmosphere by a Vertical Jet after Interacting with a Horizontal Disk

Domenico Paladino¹, Ralf Kapulla¹, Guillaume Mignot², Sidharth Paranjape³, Simon Suter¹, Myeong-Seon Chae¹, Yago Rivera¹, Nabil Ghendour¹, Christiph Hug¹

1: Paul Scherrer Institut, Switzerland; 2: Oregon State University, United States of America; 3: OST – Ostschweizer Fachhochschule, Switzerland

Experimental Study on Flow-induced Vibration of Plate-type Fuel Assembly

Shuai Liu, Bing Ren, Jie Ding, Jie Zhang, Jingya Sun, Yu Dang, Fujun Gan, Heting Sun, Chaozhu Zhang

Shanghai Nuclear Engineering Research and Design Institute Co.Ltd., China, People's Republic of

Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment

Cam Binh Pham, Grant Hawkes, Nancy Lybeck, Courtney Otani, Paul Demkowicz

Idaho National Labaratory, United States of America

Modeling of the Molten Salt Fast Reactor Transient Behavior based on the Modified Point Reactor Kinetics Model

Thanh Hung Nguyen, Yitung Chen

University of Nevada, United States of America

Development for Integrated System-Level Analysis Capabilities in SAM for Molten Salt Reactors

Rui Hu¹, Travis Mui¹, Robert Salko², Tingzhou Fei¹, Daniel O’Grady¹, Ling Zou¹, Huihua Yang³, Wei Ji³

1: Argonne National Laboratory, United States of America; 2: Oak Ridge National Laboratory, United States of America; 3: Rensselaer Polytechnic Institute, United States of America

Experimental Methodology for Forced Convection Heat Transfer in Molten Salt with Volume Internal Heat Source

Shanwu Wang¹, Hui Deng¹, Pinyan Huang¹, Hongxiang Yu¹, Ying Cao², Chong Zhou¹, Yang Zou¹

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

Influence of an Internal Heat Source on Turbulent Wall cooling Heat Transfer in a Circular Pipe

Dong-Hyuk Park, Bum-Jin Chung

KyungHee University, Korea, Republic of

Effect of Uncertainties in the MSRE Model Part 1: Salt Properties, SPECTRA / SUE Analysis

Marek Stempniewicz, Eric de Geus, Dirk Visser, Christian Fedon, Ferry Roelofs, Fajar Pangukir

NRG, Netherlands, The

Effect of Uncertainties in the MSRE Model Part 2: Delayed Neutron Precursors, SPECTRA / SUE Analysis

Marek Stempniewicz, Eric de Geus, Dirk Visser, Christian Fedon, Ferry Roelofs, Fajar Pangukir

NRG, Netherlands, The

Mass and Energy Release Analysis for Postulated Main Steam Line Break Accident in APR1000 Using SPACE-ME Code

Jisu Kim, Sung Yong Kim, Ye Eun An, Sang Jin Lee, Seong Ho Jee, Min Shin Jung, Ung Soo Kim

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

Experimental Study on Spray Activation in a Containment Atmosphere with Superheated Steam Conditions during a Design Basis Accident

Myeong-Seon Chae¹, Domenico Paladino¹, Ralf Kapulla¹, Ghendour Nabil¹, Yago Rivera¹, Simon Suter¹, Christoph Hug¹, Mira Jreissaty², Jean-Luc Vacher²

1: Paul Scherrer Institut (PSI), Switzerland; 2: Électricité de France (EDF), France

Experimental Test Results of the for ISP-52: NEA/ETHARINUS Project Contribution to DEC-A Safety Assessment

Martina Adorni¹, Anis Bousbia Salah², Simon Philipp Shollenberger³, Lars Dennhardt³, Omar Sharief Al-Yahia⁴, Alessandro Del Nevo⁵

1: OECD Nuclear Energy Agency (NEA), France; 2: BEL V, Belgium; 3: Framatome, Germany; 4: PSI, Switzerland; 5: ENEA, Italy

Simulations of a Station Black-Out with Extended Special Emergency Safety Systems and Automatic Partial Cooldown

Davide Papini, Peter Sarkadi, Reinhold Horstmann, Michael Hauck, Rainer Kaulbarsch

NPP Gösgen (KKG), Switzerland

VIKTORIA Experiments in the Frame of R&D Project on Sump Filtration during a Loss of Coolant Accident : Effect of the Type of Filter, the Mass of Fiber and the Presence of Zinc

Georges Repetto¹, Jean-Francois Trigeol¹, Vojtech Soltesz²

1: Autorité de Sûreté Nucléaire et de Radioprotection, France; 2: VUEZ A.S, Slovakia

Safety Analyses of Events in Shutdown Modes of VVER-1000

Pavel Kral¹, Radim Honcarenko², Zbynek Vymetalik²

1: UJV Rez, Czech Republic; 2: CEZ, Czech Republic

Validation of NekRS for Flow-splitting in a Wire-wrapped Fuel Pin Bundle

Dillon Shaver¹, Adam Kraus¹, Aleksandr Obabko¹, Sterling Harper², Monica Pham², SuJong Yoon²

1: Argonne National Laboratory, United States of America; 2: TerraPower, LLC, United States of America

Chemical Kinetic Uncertainty Quantification in Hydrogen Combustion Computational Fluid Dynamics Simulation for ENACCEF2 Experiment

Kosuke Motegi, Toshinori Matsumoto, Hiroyuki Shiotsu

Japan Atomic Energy Agency, Japan

Validation of a CFD Model for Steam Condensation in the Presence of a Noncondensable Gas under Conjugate Heat Transfer Conditions

Abdelouahab Dehbi¹, Omar Al-Yahia¹, Lina Si Salah², Mohamed Aksouh²

1: Paul Scherrer Institut, Switzerland; 2: University of Science and Technology Houari Boumediene, Algeria

Validation of the Generalized Multiphase CFD Modelling Approach GENTOP Using Fluent

Thomas Höhne¹, Maycon Ferreira²

1: Helmholtz-Zentrum Dresden - Rossendorf (HZDR), Germany; 2: University of Almeria, Spain

RANS Validation of Two-Layer Scalar Diffusivity Model for High Schmidt Mass Transfer Problems

Kin Wing Wong, Ignas Mickus, Dmitry Grishchenko, Pavel Kudinov

KTH Royal Institute of Technology, Sweden

Validation of Multi-Phase CFD for Compact Steam Generator Application

Witiwat Jiragoontansiri, Koroush Shirvan

Massachusetts Institute of Technology, United States of America

New IAEA Network on Experimental Testing and Validation for Design and Safety Analysis Computer Codes for SMR and Advanced Reactor Designs: NEXSHARE

Xiaoyu Zhang¹, Eve-Lyne Pelletier¹, Martina Adorni², David Hummel³, Andrew Morreale⁴

1: International Atomic Energy Agency; 2: OECD Nuclear Energy Agency; 3: Generation IV International Forum; 4: Canadian Nuclear Laboratories, Canada

Main Outcomes of the McSAFER Project Devoted to Numerical and Experimental Investigations for the Safety Assessment of Water-cooled SMRs

Victor Hugo Sanchez Espinoza¹, Heikki Suikkanen², Ville Valtavirta³, Marek Bencik⁴, Sören Kliem⁵, Cesar Queral⁶, Barbara Vezzoni⁷, Alan Charles⁸, Paul van-Uffelen⁹, Marcus Seidl¹⁰, Christophe Schneidesch¹¹, Dmitry Grishchenko¹², Hector Lestani¹³

1: Karlsruhe Institute of Technology (KIT), Germany; 2: LUT University, Finland; 3: VTT, Finland; 4: UJV Rez a.s, Czech Republic; 5: Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Germany; 6: Universidad Politécnica de Madrid (UPM), Spain; 7: CEA, France; 8: Global Amentum, United States of America; 9: Joint Research Centre Karlsruhe, Germany; 10: PreussenElektra GmbH, Germany; 11: Tractebel Engineering S.A, Germany; 12: PreussenElektra GmbH, Sweden; 13: Comision Nacional de Energia Atomica (CNEA), Argentina

Analysis of Dynamic Response of Passive ECCS Valves Using MARS-KS Code Based Scheme, SEMICOM

Young Seok Bang, Youngjae Park, You Cho Choi, Seong-Su Jeon, Soon-Joon Hong

Future and Challenge Technology Co., Korea, Republic of

Ensuring Assessment of Safety Innovations for Light Water SMR: Experimental Testing, Code Validation, and Reliability Assessment in the Horizon Euratom EASI-SMR Project

Fulvio Mascari¹, Franck Morin², Petr Bizek³, Nicolas Sobecki⁴

1: ENEA, Italy; 2: CEA, France; 3: UJV, Czech Republic; 4: EDF, France

Convolutional Prototype Learning-based Open Set Recognition Fault Diagnosis Method for Nuclear Power Plant Faults

Jiangkuan Li¹, Shangcai Zheng², Jiaoshen Xu¹, Sichao Tan¹, Ruifeng Tian¹

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

Effects of Heat Pipe Temperature Oscillation on the Operation of Supercritical CO2 Heat Pipe Cooled Reactor

Guanghui Jiao, Genglei Xia, Tao Zhou, Jianjun Wang

Harbin Engineering University, China, People's Republic of

Experimental Analysis of Non-Condensable Helium and Steam Distribution Due to Condensation in the CIGMA Facility Simulating the Reactor Building

Ari Hamdani, Shu Soma, Satoshi Abe, Yasuteru Sibamoto

Japan Atomic Energy Agency, Japan

Comparison between EDF MAAP5.04 and EPRI MAAP6 Codes on Hypothetical Severe Accidents in an Integral PWR

Jeremy Bittan, Nikolai Bakouta

Electricité de France, France

Severe Accident Progression Analyses of Loss-of-coolant Accidents with Different Break Sizes in a Typical Japanese Four-loop PWR Using MELCOR2.2

Junichi Kaneko, Wataru Kikuchi, Masashi Taira

Nuclear Regulation Authority, Japan

ASTEC V3: A Comprehensive Integral Code for Nuclear Safety Analysis and Research – Overview of Recent Applications and Perspectives

Patrick Drai, Nathalie Girault, Laure Carénini, Laurent Laborde, Julie-Anne Zambaux, Laure Cloarec, Eric Delaume, Florian Fichot, Catherine Marchetto, Sidi Souvi, Olivia Coindreau, François Virot, Matthieu Jobelin, Guillaume Astier, Francois Kremer, Karine Chevalier-Jabet, Loic Bosland, Helene Bloch, Lionel Chailan, Raphael Monod, Michael Johnson, Laurent Foucher, Alexandre Bleyer, Alain Commande, Jean-Jacques Ingremeau, Marton Szogradi

Autorité de Sûreté Nucléaire et de Radioprotection, France

Analyzing Steam Explosions During Severe Accidents in Nordic BWRs with MELCOR-TEXAS Coupling

Govatsa Acharya, Ibrahim Batayneh, Dmitry Grishchenko, Pavel Kudinov

KTH Royal Institute of Technology, Sweden

Progress in Utilizing Macroscopic Models for the Simulation of Passive Systems in the Lumped Parameter Code AC²/COCOSYS

Ivan Bakalov, Claus Spengler, Nils Reinke, Siegfried Arndt

GRS, Germany

OECD/NEA Benchmark on Artificial Intelligence and Machine Learning for Critical Heat Flux Predictions – Summary of Phase 1 Results

Jean-Marie Le Corre¹, Gregory K. Delipei², Xu Wu², Xingang Zhao³, Oliver Buss⁴

1: Westinghouse Electric Sweden AB, Sweden; 2: North Carolina State University, United States of America; 3: University of Tennessee, United States of America; 4: Nuclear Energy Agency, France

AI-informed Parameter Selection for Critical Heat Flux Prediction Models: Revisiting the Role of Inlet Conditions

Evgeny Nikitin, Sören Kliem

Helmholtz-Zentrum Dresden-Rossendorf, Germany

Assessment of the State-of-the-Art AI Methods for Critical Heat Flux Prediction

Wen Zhou, Shuichiro Miwa, Hanyu Wang, Koji Okamoto

The University of Tokyo, Japan

Deep Learning for Critical Heat Flux Regression through an Increasing-complexity Approach

Gabriele Cassetta, Lucia Sargentini, Alberto Ghione, Guillaume Damblin

CEA, France

A Data-informed Continuous Machine Learning Approach for CHF Prediction

Meiqi Song^1,2, Fabian Wiltschko², Xiaojing Liu¹, Aurelian Florin Badea², Xu Cheng²

1: Shanghai Jiao Tong University (SJTU), China, People's Republic of; 2: Karlsruhe Institute of Technology (KIT),Germany

Study of the Operation of a Passive Heat Removal System on a Light Water Small Modular Reactor with the ASTEC V3.1.2 Code

Julie-Anne Zambaux¹, Zhexi Guo², Sicong Xiao²

1: Autorité de Sûreté Nucléaire et Radioprotection (ASNR), France; 2: Singapore Nuclear Research and Safety Institute (SNRSI), Singapore

Experimental and Numerical analysis on Safety Condenser Transient Performance based on P1.2 Experiments at the PKL Facility

Ignacio Gomez-Garcia-Torano¹, Maxime Vernassiere¹, Simon Schollenberger², Lars Dennhardt², Andreas Wielenberg³, Sebastian Buchhlotz³, Massimiliano Polidori⁴, František Lahovský⁵, Omar Sharief Al-Yahia⁶, Michaël Montout⁷

1: Commissariat à l'énergie atomique et aux énergies alternatives (CEA), France; 2: Framatome GmbH, Germany; 3: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany; 4: Agenzia Nazionale per le Nuove Tecnologie, l'Energia e lo Sviluppo Economico Sostenibile (ENEA), Italy; 5: Nuclear Research Institute Řež (UJV), Switzerland; 6: Paul Scherrer Institut (PSI), Switzerland; 7: Electricité de France (EdF), France

Reliability Assessment of the BWRX-300 Passive Isolation Condenser System: Addressing Uncertainties in Two-Phase Natural Circulation Flow Modeling

Graeme Trundle¹, Sergey Galushin², Sean Roshan¹, Sevostian Bechta¹, Michael Söderström³, Anders Olsson²

1: Royal Institute of Technology (KTH), Sweden; 2: Vysus Group, Sweden; 3: Vattenfall AB, Sweden

Numerical Study on Steady-State Characteristics of Two-Phase Loop Thermosiphon in a Novel Small Modular Reactor

Xubin Wu, Wentao Hao, Wenwen Zhang, Zhenlei Liu, Weihua Li, Xingtuan Yang

Institute of Nuclear and New Energy Technology, Tsinghua University, China, People's Republic of

Update on Standard Wall Modeled Large Eddy Simulation on a Few Validation Test-cases

Jean-François Wald¹, Leo Deperne¹, Luc Bertolotti¹, Samuel Gaucher¹, Clément Colas¹, Sofiane Benhamadouche^1,2

1: EDF R&D, France; 2: CEREA, France

Wall-resolved LES for Predicting Turbulent Flow through Tube Bundles

Sofiane Benhamadouche

EDF R&D, France

Simulation of NACIE Tests with Thermal Hydraulics Systems Codes

Konstantin Mikityuk¹, Anton Moisseytsev², Ossama Abedelhalim³, Luca Ammirabile⁴, Ilya Aulov⁵, Akhmed Baisov⁵, Barbara Calgaro⁶, Gianfranco Caruso⁷, Zhao Chen⁸, Pietro Cioli Puviani⁹, Cristiano Ciurluini⁷, Tommaso Del Moro⁹, Ivan Di Piazza⁹, Daniel Dupleac¹⁰, Anton Ekimov¹¹, Paolo Ferroni¹², Nicola Forgione¹³, Fabio Giannetti⁷, Wenjun Hu¹⁴, Olga Ilyasova¹⁵, Vladimir Kriventsev¹⁶, Sung Jin Lee¹⁷, Jun Liao¹², Pierdomenico Lorusso⁹, Daniele Martelli⁹, Mirea Mladin¹⁸, Evgenii Moiseenko¹⁵, Andrei Moiseev¹¹, Nikoleta Morelova¹⁶, Nastasya Mosunova¹⁵, Roxana-Mihaela Nistor-Vlad¹⁰, Marilena-Luminita Nitulescu¹⁸, Dan Ogrady², Fajar Pangukir¹⁹, Oriol Parera Villacampa⁴, Byung Ha Park²⁰, Andrea Pucciarelli¹³, Lixia Ren¹⁴, Zhihao Ren⁸, Ferry Roelofs¹⁹, Konstantin Sergeenko¹¹, Pietro Stefanini³, Mariano Tarantino⁹, Rachel Thomas², Vyacheslav Vereshchagin¹¹, Vasily Volkov⁵, Dalin Zhang²¹, Lei Zhou¹⁴

1: PSI, Switzerland; 2: ANL, United States of America; 3: UNIPI, Italy; 4: JRC, EC; 5: Gidropress, Russian Federation; 6: newcleo, Italy; 7: La Sapienza, Italy; 8: CNPRI, China, People's Republic of; 9: ENEA, Italy; 10: PUB, Romania; 11: NIKIET, Russian Federation; 12: Westinghouse, United States of America; 13: UNIPI, Italy; 14: CIAE, China, People's Republic of; 15: IBRAE RAN, Russian Federation; 16: IAEA, Austria; 17: Fauske & Associates, United States of America; 18: RATEN ICN, Romania; 19: NRG, Netherlands, The; 20: KAERI, Korea, Republic of; 21: XJTU, China, People's Republic of

Evaluation of CTF and DRACCAR Capabilities for Reflood Modelling with RBHT-I Open Tests

Lucia Rueda Villegas, Adrian Sabater Alcaraz, Jinzhao Zhang

TRACTEBEL, Belgium

Validation of Domain Overlapping Coupling Between SAM and MOOSE-Subchannel Using NACIE Test

Gang Yang, Nicolas Bodet, Anton Moisseytsev, Ling Zou, Rui Hu

Argonne National Laboratory, United States of America

Comparisons of ASTEC and DRACCAR Codes Results Against COAL B0 Experiments under Bundle Reflooding Conditions

Pietro Maccari, Marica Eboli, Alessandro Del Nevo

ENEA – Nuclear Department, Experimental Engineering Division (NUC-ING), Italy

HYBISCUS-II: Numerical Simulation of a Pressurized Thermal Shock on a Reduced Scale Experiment

Alexis Thibault Marie Berny¹, Cecile Demathieu², Joël Nibas², Alain Ungar²

1: Université Paris Saclay, CEA, France; 2: EDF R&D Lab Chatou, France

Numerical Activities of PASI Experiments for Passive Containment Cooling in the European PASTELS Project

Franck David¹, Paul Dene¹, Gian Marco Grippo³, Julie Anne Zambaux⁵, Sebastian Buchholz⁴, Joonas Telkka⁶, Omar Al Yahia⁷, Adam Kecek⁸, Zbynek Parduba⁸, Augustin Brissart², Massimiliano Polidori³, Ignacio Gomez²

1: EDF R&D, France; 2: CEA, France; 3: ENEA , Italy; 4: GRS, Germany; 5: IRSN, France; 6: LUT, Finland; 7: PSI, Switzerland; 8: UJV, Czechia

Experimental Study of Two-phase Flow in a Four-by-four Unheated Rod Bundle for Validation of Thermal-hydraulics Simulation Codes

Muhammad Ilham, Taku Nagatake, Shinichiro Uesawa, Ayako Ono

Japan Atomic Energy Agency, Japan

Assessment of Spacer Grid Effects and Flow Development in a Triangular Rod Bundle: A PIV-DNS Cross-Comparison

Danila Trane¹, Mattia Grespan¹, Enrico Stalio², Diego Angeli¹

1: Department of Sciences and Methods for Engineering, University of Modena and Reggio Emilia, Italy; 2: Department of Engineering Enzo Ferrari, University of Modena and Reggio Emilia, Italy

Evaluation on Two Different Mixing Vanes by PIV Experiment in 5x5 Rod Bundle

Junya Inoue¹, Yoshitaka Mizutani¹, Yasushi Hirai¹, Tatsuya Sasakawa¹, Shigeo Hosokawa²

1: Nuclear Fuel Industries, Ltd., Japan; 2: Kansai University, Japan

Three-dimensional Turbulent Flow Measurements in a 6 × 6 Fuel Rod Bundle

Anis Rezaiguia², Roberto Capanna¹, Charles Fort¹, Emmanuel Lo Pinto², Guillaume Ricciardi², Philippe Bardet¹

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

Three-dimensional Void fraction Distribution of Transient Boiling Two-phase Flow in a Heated 5×5 Rod Bundle During Depressurization Process

Shota Ueda¹, Takahiro Arai¹, Masahiro Furuya¹, Riichiro Okawa¹, Atsushi Ui¹, Wataru Sakuma²

1: Central Research Institute of Electric Power Industry, Japan; 2: Mitsubishi Heavy Industries, Ltd., Japan

Investigation of the Post-CHF Heat Transfer Modeling based on the Large Scale RBHT Reflood Data Compilation and Assessment

Yue Jin¹, Andrew Ireland², Stephen Bajorek², Kirk Tien², Chris Hoxie², Fab-Bill Cheung³

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

How Good is “Good Agreement”? Considerations when Comparing Experiments with Simulations for Rod Bundles with Wire Spacers

Julio Pacio¹, Ferry Roelofs², Heleen Uitslag-Doolaard², Akshat Mathur², Dillon Shaver³, Elia Merzari⁴

1: Belgian Nuclear Research Centre (SCK CEN), Belgium; 2: Nuclear Research and Consultancy Group (NRG), The Netherlands; 3: Argonne National Laboratory (ANL), United States of America; 4: Pennsylvania State University (PSU), United States of America

Analyzing the Effect of Deformed Pins in LMFR Rod Bundles

Ferry Roelofs¹, Shubham Dalvi¹, Heleen Uitslag-Doolaard¹, Markus Daubner², Karsten Litfin², Manuela Profir³, Vincent Moreau³, Pietro Cioli Puviani⁴, Daniele Martelli⁴, Ivan Di Piazza⁴, Sara Gonzalez Ruiz⁵, Luis Carbonelle⁵, Matilde Fiore⁵, Mushin Can Akkurt⁵, Philippe Planquart⁵, Julio Pacio⁶

1: NRG, Netherlands, The; 2: KIT, Germany; 3: CRS4, Italy; 4: ENEA, Italy; 5: VKI, Belgium; 6: SCK CEN, Belgium

Numerical Simulation of Flow and Heat Transfer Characteristics for LBE in Plate-type Bundle Fuel Assembly with LES-Smagorinsky Lilly Model

Feiran Wang^1,2, Zhengjie Yang^1,2, Jiming Wen^1,2, Bangyang Xia^3,4, Chong Chen^3,4, Xue Zhang^3,4, Gongjian Xie¹, Ruifeng Tian^1,2, Sichao Tan^1,2

1: College of Nuclear Science and Technology, Harbin Engineering University, China, People's Republic of; 2: Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, Harbin Engineering University, China, People's Republic of; 3: National Key Laboratory of Nuclear Reaction Technology, China, People's Republic of; 4: State Key Laboratory of Advanced Nuclear Energy Technology, China, People's Republic of

Thermal-hydraulic and Safety Analysis of a Horizontal Assembly in the LFR during Flow Blockage Accident

Di Wu^1,2, Zhibo Gao^1,2, Minyang Gui^1,2, Jiaxin Zhang³, Jie Cheng^1,2, Xu Han^1,2, Xiaobo Zeng^1,2, Jianjun Wang^1,2

1: College of Nuclear Science and Technology, Harbin Engineering University, China, People's Republic of; 2: Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment, Harbin Engineering University, China, People's Republic of; 3: Nuclear Power Institute of China, China, People's Republic of

Local Hot Spots of the Wire-wrapped Pin Bundle in the Liquid Metal Cooled Reactors

Taehwan Ahn^1,2, Wilhelm-Martin Bissels², Victor Petrov^1,2, Annalisa Manera^1,2

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

Uncertainty Analysis of Rod Bundle Channel for Lead-Bismuth Reactors Based on Sub-channel Code

Deyan Kong, Di Wu, Jie Cheng, Xu Han, Xiaobo Zeng, Jianjun Wang

Harbin Engineering University, China, People's Republic of

Uncertainty propagation and Global Sensitivity Analysis based on the Hilbert-Schmidt Independence Criterion measures. Application to a load rejection transient in a Pressurized Water Reactor

Paolo Olita, Amandine Marrel

French Atomic Energy and Alternative Energies Commission, France

Verification of Multi-scale Post-process Method on PSBT Subchannel Experiment and Application to Rowe and Angle Experiment

Filippo Arlotti¹, Xavier Manchon¹, Jorge Perez-Manes¹, Nathalie Seiler¹, Nicolas Rimbert², Jean-Marc Labit³, Stéphane Mimouni⁴

1: CEA, DES, IRESNE, Cadarache, F-13108 Saint-Paul-lès-Durance, France; 2: Université de Lorraine, CNRS LEMTA, F-54000 Nancy, France; 3: CEA Saclay, F-91191 Gif-sur-Yvette, France; 4: Electricité de France, R&D Division, F-78401, Chatou, France

Leveraging Multiple Fidelities for Thermal-hydraulics Uncertaintyanalyses of Fuel Assemblies Subjected to Deformation

Matilde Fiore, Silvania Lopes, Lilla Koloszar, Philippe Planquart

von Karman Institute for Fluid Dynamics, Belgium

Development of a Robust Stochastic Framework for Numerical Error Estimation and Uncertainty Quantification in Unsteady Flow Simulations

Yu-Jou Wang¹, Emilio Baglietto¹, Patrick McGah², Monica Pham²

1: Massachusetts Institute of Technology; 2: TerraPower, LLC

Toward Simplified, Scalable Detonation Modeling: Independent Validation of the Generalized Turbulent Flame Closure Approach for DDT in Hydrogen Mixtures

Mantas Povilaitis, Stephen Oluwabukunmi Adesina, Julius Venckus

Lithuanian Energy Institute, Lithuania

Validation of the Open Source TUAS Using Coupled Natural Circulation Data from CIET

Theodore Kay Chen Ong¹, Sicong Xiao¹, Per F. Peterson²

1: National University of Singapore (NUS), Singapore; 2: University of California, Berkeley, United States of America

Characteristic Features of Fission Product Behavior by CINEMA and MELCOR Codes during Severe Accidents of OPR1000

Se Hee Kwon¹, Juhyeong Lee¹, Joon Young Bae¹, Yujin Kim¹, Joon-Eon Yang¹, JinHo Song¹, Sung Joong Kim^1,2

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

Experimental Investigation of Pressure Drop in Single and Two-Phase Flow Through Sand Packed Beds

Aimad Bouloudenine, Liangxing Li, Shang Shi, Zutao Xiang

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

Using Calibrated Sodium Data for Preliminary Validation of the SRT Code for Advanced Reactors

Dong Hoon Kam¹, Dave Grabaskas¹, Kyle Becker², Mark Anderson², Tyler Starkus¹

1: Argonne National Laboratory, United States of America; 2: University of Wisconsin-Madison, United States of America

An Update of the Models Related to the In-Vessel Retention Strategy in the MAAP6 Code

Nikolai Bakouta, Jeremy Bittan

Electricité de France, France

Progress in the Development of the ContainmentFOAM CFD Package for Analysis of Current and Future LWR Containment Phenomena

Stephan Kelm¹, Allen George², Ruiyun Ji³, Carlos Vazquez-Rodriguez¹, Khaled Yassin¹, G. Vijaya Kumar⁴, Xiongguo Liu¹, Daniel Schumacher¹, Karl Sturm⁵, Leon Thelen¹, Martin Lövenich¹, Claudia Druska¹, Astrid Kuhr¹

1: Forschungszentrum Juelich GmbH, Germany; 2: Forschungszentrum Juelich GmbH and Karlsruhe Institute of Technology, Germany; 3: Forschungszentrum Juelich GmbH and Universität der Bundeswehr Muenchen, Germany; 4: Forschungszentrum Juelich GmbH, Germany and Indian Institute of Technology Madras, India; 5: Forschungszentrum Juelich GmbH and RWTH Aachen University, Germany

Uncertainty and Sensitivity Analysis of MELCOR-Based Source Term Predictions for the PHEBUS FPT-1 Experiment

Han Sol Park, Yeon-Gun Lee

Sejong University, Korea, Republic of

Use of PINNs to Improve CHF Model Behaviour

Yi Meng Chan

KTH, Sweden

Probabilistic/Interpretable Neural Network Frameworks for Flow Boiling CHF Prediction in Circular Tubes

Kyung Mo Kim¹, Juhyung Lee², Mooneon Lee², Hyuk Kwon², Han Seo²

1: Korea Institute of Energy Technology (KENTCH), Korea, Republic of; 2: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of

Critical Heat Flux Prediction in Round Tubes Using AI/ML: A Comparison of XGBoost and MLP Models

Mooneon Lee¹, Juhyung Lee¹, Hyuk Kwon¹, Dae-Hyun Hwang¹, Kyung Mo Kim²

1: Korea Atomic Energy Research Institute, Korea, Republic of; 2: Korea Institute of Energy Technology, Korea, Republic of

Evaluating the Performance of Diffusion Models for Scientific Data Augmentation - a Case Study with Critical Heat Flux

Farah Raed Hussein Alsafadi, Xu Wu

North Carolina State University, United States of America

Investigation of Pool and Containment Thermalhydraulic Behavior Using the 3D Module of CATHARE-3

Ignacio Gomez-Garcia-Torano¹, Christophe Bourcier¹, Julie-Anne Zambaux², Jeremy Bittan³

1: Commissariat à l'énergie atomique et aux énergies alternatives (CEA), France; 2: Institut de Radioprotection et de Sûreté Nucléaire (IRSN), France; 3: Electricité de France (EdF), France

Study of Flow Distribution of High Power Density Plate-Type PWR by Two-Phase Neutronics-Thermohydraulics Coupling Code

Guodong Liu¹, Ying He¹, Junren Hou¹, Meiming Qiu¹, Xingyu Zhao¹, Shanfang Huang¹, Kan Wang¹, Zhigang Li^2,3, Chuan Lu^2,3

1: Tsinghua University,China, People's Republic of; 2: Nuclear Power Institute of China, China, People's Republic of; 3: National Key Laboratory of Nuclear Reactor Technology, China, People's Republic of

Prediction of Multiphase Flow and Flow-induced Forces in a Cross-flow Tube Bundle with a Morphology-adaptive CFD Model

Marco Colombo¹, Daniele Vivaldi²

1: University of Sheffield, United Kingdom; 2: Autorité de Sûreté Nucléaire et de Radioprotection (ASNR), France

Modeling a Flexible Operation Scenario in a KWU-PWR Reactor using RELAP5/PARCS

Bárbara Navarro¹, Teresa Barrachina¹, Rafael Miró¹, Gumersindo Verdú¹, Marina García-Fenoll², José María Posada²

1: Universitat Politècnica de València, Spain; 2: Centrales Nucleares Almaraz-Trillo (CNAT), Spain

Multiscale Modelling of Forced-to-natural Circulation Experiments in Heavy Liquid Metal Test Loop NACIE

Andrea Pucciarelli¹, Pietro Stefanini¹, Ossama Halim¹, Nicola Forgione¹, Rajendrakumar Murugesan², Natesan Kumaresan², Amit Kumar Chauhan², Dhrumil Ganatra², Mohammed Muaaz Mohamed Dilshad Hussain³, Fajar Pangukir³, Akshat Mathur³, Pietro Cioli Puviani⁴, Tommaso Del Moro⁵, Dalin Zhang⁶, Yixin Zhang⁶, Vladimir Kriventsev⁷, Ivan di Piazza⁸

1: University of Pisa, Italy; 2: IGCAR, India; 3: NRG, Netherlands, The; 4: Politecnico di Torino / ENEA, Italy; 5: Sapienza University of Rome / ENEA, Italy; 6: Xi'an Jiaotong University, China, People's Republic of; 7: IAEA; 8: ENEA Brasimone Research Centre, Italy

Visualization Analysis of Performance of Boiling Heat Transfer on Micro-cavity Surface According to Cavity Diameter

Do Yeon Kim¹, Seon Ho Choi³, Su Cheong Park², Dong In Yu¹

1: Pukyong National University, Korea, Republic of; 2: Dong-a University, Korea, Republic of; 3: Pohang Accelerator Laboratory, Korea, Republic of

Experimental Research of Wicking Degradation Effect on Boiling Heat Transfer Characteristics with Nanostructured Surface

Jian Zhou, Longchang Tang, Wei Xu, Xiaojing Liu

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

Visual Study of Subcooled Boiling based on Femtosecond Laser Modified Surface

Mingze Cao^1,2, XIao Yan¹, Dianchuan Xing¹, jianjun Xu¹, Yanlin Wang¹, Tianzhou Xie²

1: Nuclear Power Institute of China, China, People's Republic of; 2: State Key Laboratory of Advanced Nuclear Energy Technology, China, People's Republic of

Heat Transfer Enhancement for Nucleate Boiling via Microlayer Evaporation on Micro-pillar Arrayed Surface

Wei Ding¹, Jinming Zhang¹, Uwe Hampel^1,2

1: Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Germany; 2: Technische Universität Dresden, Germany

Hydrodynamic and Thermal Investigation of Oxide Layer Microscale Surface Features on Nucleate Boiling

Matthew Val Meyers¹, Patrick Lewis², Ryan Tunstall², Edward Smith³, Giovanni Giustini¹, Alex Skillen¹

1: University of Manchester, United Kingdom; 2: Rolls Royce, United Kingdom; 3: Brunel University, United Kingdom

Assessment of Correlations for Point of Net Vapor Generation using Direct Visual Observation

Taiyang Zhang¹, Joseph L. Bottini²

1: The Ohio State University, United States of America; 2: United States Military Academy, United States of America

Measurement of Interfacial Phenomena Near CHF in High Pressure Water Flows Using High-Speed X-Ray Radiography

Yang Liu, David Novog

McMaster University, Canada

Scalability of Validation Data for Safety Evaluation of Water-cooled Nuclear Reactors

Chul-Hwa Song, Kyoung-Ho Kang, Ki-Yong Choi

Korea Atomic Energy Research Institute, Korea, Republic of

Large Scale Best-Estimate Plus Uncertainty Analysis of LOFT L2-5 Experiment

David Aumiller, Gabriel Kooreman, Michael Meholic

NNL, United States of America

The Role of BEPU Methodology in Nuclear Safety Demonstration

Julien Beaucourt, Fabrice Fouet, Pierre Ruyer, Franck Dubois

ASNR (Autorité de Sûreté Nucléaire et de Radioprotection), France

A Global Dialogue on Broadening Industrial Applications of BEPU: Outcomes of a Panel Session at the BEPU-2024 Conference

Jinzhao Zhang¹, Martina Adorni², Alberto Ghione³, Lucia Sargentini³, Vincent Larget⁴, Robert Martin⁵, Dong Gu Kang⁶, Alessandro Petruzzi⁷

1: TRACTEBEL, Belgium; 2: OECD/NEA, France; 3: CEA, France; 4: EDF, France; 5: USNRC, United States of America; 6: KINS, Korea, Republic of; 7: NINE, Italy

Research on Thermal Safety of Intensive Spent Fuel Dry Storage Facility for Heavy Water Reactor

Zhen Xu, Bing Ren, Zhan Liu, Qin Ye

Shanghai Nuclear Engineering Research & Institute CO.LTD, China, People's Republic of

BEPU LBLOCA Analysis Including Zirlo, FeCrAl and Cr-coated Zry Cladding

David Canal¹, Cesar Queral¹, Emilio Castro-Gonzalez¹, Jorge Sanchez-Torrijos²

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

Steam Line Break with Blowdown of Multiple Steam Generators

Joakim Holmström, Magnus Holmgren

Ringhals AB, Sweden

Parametric TRACE Code Survey of Fusion DEMO Reactor on Three Representative LOCA Scenarios

Shun Nukaga¹, Masahiro Furuya¹, Yoji Someya², Mitsuya Kato², Yoshiteru Sakamoto²

1: Waseda University, Japan; 2: National Institutes for Quantum Science and Technology, Japan

A Novel Parametric Dynamic Mode Decomposition Formulation: Application to Magnetohydrodynamic Liquid Metal Flows

Matteo Lo Verso¹, Stefano Riva¹, Carolina Introini¹, Eric Cervi¹, Francesca Giacobbo¹, Matteo Di Prinzio², Marco Caramello², Laura Savoldi³, Antonio Cammi^4,1

1: Politecnico di Milano, Italy; 2: Ansaldo Nucleare SpA, Italy; 3: Politecnico di Torino, Italy; 4: Khalifa University, United Arab Emirates

Direct Numerical Simulation of Magneto-Convection at Low Magnetic Reynolds Number

Jake Ineson¹, Alex Skillen¹, Aleksander Dubas²

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

Coupled CFD and Neutronics for Accidents and Transients in Fusion Blankets

Arpan Sircar, Jin Whan Bae, Katarzyna Borowiec, Vittorio Badalassi, Cami Collins

Oak Ridge National Laboratory, United States of America

Thermal-hydraulic Analysis in Support of the Design of Water Loop Experimental Facility for Testing Mock-ups in Fusion-like Environment

Alessandra Vannoni¹, Giorgio Mongiardini², Cristiano Ciurluini², Bruno Gonfiotti¹, Pietro Arena¹, Marica Eboli¹, Ranieri Marinari¹, Fabio Giannetti², Alessandro Del Nevo¹

1: ENEA, Italy; 2: Sapienza University of Rome, Italy

On the Development of Tokamak-based Conventional Power Plants

Sara Perez-Martin

Karlsruhe Institute of Technology, Germany

Numerical Analysis of a WCLL BB TBM Mock-up to be Installed in Water Loop Facility

Giorgio Mongiardini¹, Alessandra Vannoni², Cristiano Ciurluini¹, Bruno Gonfiotti², Fabio Giannetti¹, Marica Eboli², Pietro Arena², Pietro Maccari², Alessandro Del Nevo²

1: Sapienza University of Rome, Italy; 2: ENEA – Nuclear Department, Italy