Conference Agenda

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

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

Fission Products Scrubbing in Water Ponds during Severe Accidents: An Efficient Means of Attenuating Source Term

Luis Herranz

CIEMAT, Spain

Experimental Study on the Influence of Epoxy Patterns of Bi-conductive Surfaces on Pool Boiling

Longchang Tang, Wei Xu, Yan Liu, Xiaojing Liu

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

Experimental Study of the Nucleate Flow Boiling to Convective Flow Boiling Transition

Carlos Alberto Dorao, Maria Fernandino

Norwegian University of Science and Technology, Norway

Quantitative Heat Flux Prediction from Images Using Convolutional Neural Networks with Multi-Branch Convolutions

Mengqi Wu¹, Zhen Zhang¹, Yongyong Wu¹, Nan Gui¹, Xingtuan Yang¹, Jiyuan Tu^1,2, Shengyao Jiang¹

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

Study of Subcooled Flow Boiling at Low Pressure Conditions Using Eulerian-Eulerian Multiphase Flow Model Coupled with Force Balance Model

Nikhil Chitnavis¹, Harish Pothukuchi^1,2, B.S.V. Patnaik¹

1: Indian Institute of Technology Madras, India; 2: Indian Institute of Technology Jammu, India

Microlayer and Contact Line Dynamics under Different Heat Fluxes at Nucleate Boiling

Corentin Le Houedec¹, Boštjan Zajec¹, Cassiano Tecchio¹, Benjamin Cariteau¹, Pere Roca i Cabarrocas², Pavel Bulkin², Vadim S. Nikolayev³

1: Université Paris-Saclay, CEA, STMF, France; 2: Institut Polytechnique de Paris, Ecole Polytechnique, LPICM, CNRS, France; 3: Université Paris-Saclay, CEA, SPEC, CNRS, France

Rapid Microlayer Depletion Induced by Bubble Coalescence in Nucleate Pool Boiling

Sai Raja Gopal Vadlamudi¹, Jinming Zhang¹, Uwe Hampel^1,2, Wei Ding¹

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

Direct Numerical Simulation of Single Bubble Dynamics and Associated Heat Transfer: Sensitivity Analysis on Wall Thermal Properties

Linkai Wei¹, Guillaume Bois¹, Vadim S. Nikolayev², Benoit Gwinner³, Solène Delgado³

1: Université Paris-Saclay, CEA, Service de Thermo-hydraulique et de Mécanique des Fluides, France; 2: Service de Physique de l’Etat Condensé, CEA, CNRS, Université Paris–Saclay, France; 3: Université Paris-Saclay, CEA, Service de recherche en Corrosion et Comportement des Matériaux, France

Dynamical System Scaling Application to Bubble Dynamics

Grant Justin Hendrickson, Qiao Wu

Oregon State University, United States of America

Study on Bubble Nucleation and Growth Behaviors Under Supersaturated Conditions in Nitrogen-pressurized Reactors

Xin Lyu, Junlian Yin, Dezhong Wang

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

Investigating Bubble Motion in Downward Flow through Perforated Plates

Nakjun Choi¹, Donkoan Hwang¹, Siyeh Kim², Jeyeong Cheon², HangJin Jo^1,2

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

Local Bubble Characteristics of Subcooled Boiling Flow in an Annular Channel under a Wide Range of Pressure Conditions

Jinyeong Bak, Dongmin Lim, Dongwon Jeong, Minhong Cho, Sanggyun Nam, Manh Long Doan, Byongjo Yun

Pusan National University, Korea, Republic of

Numerical Simulation for Effects of Steam Mass Fraction on Condensation Heat Fluxes from Saturated Steam and Air Mixture on a Vertical Flat Plate

Michio Murase, Toshiya Takaki, Koji Miyoshi

Institute of Nuclear Safety System, Inc., Japan

Experimental Study on Vibration Characteristics of Heat Transfer Tube during Condensation

Haoyu Ruan^1,2, Dongyang Li^1,2, Shiyuan Jiang^1,2, Xue He^1,2, Ruifeng Tian^1,2, Sichao Tan^1,2

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

Integrating Subcooled Flow Boiling and Film Condensation in CFD Modeling of Loop Thermosiphon

Quoc-Tuan Le, Byoung Jae Kim

Chungnam National University, Korea, Republic of

Potential Retention of Fission Products in a Two-phase Flow Problem: Focus on the Hydrodynamics in Pool Scrubbing

Fouzia Djeriouat^1,2, Catherine Marchetto¹, Philippe Nerisson¹, Maxime Chinaud², Jean Denis¹, Olivier Vauquelin²

1: Autorité de Sûreté Nucléaire et Radioprotection (ASNR), France; 2: Institut Universitaire des Systèmes Thermiques Industriels (IUSTI), France

Visulization Study of Film-wise Condesation Heat Transfer on Helical Tubes

Myeonggi Cha, HangJin Jo

POSTECH, Korea, Republic of

Validation Analyses of Natural Circulation and Condensation for MELCOR 2.2 based on PANDA Facility Experiment

Mateusz Michal Malicki, Terttaliisa Lind

Paul Scherrer Institut, Switzerland

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

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

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

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

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

Kevin Zwijsen

Nuclear Research and Consultancy Group, Netherlands, The

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

Taemin Ahn, Armanto Pardamean Simanjuntak, Jaeyoung Lee

Handong Global University, Korea, Republic of

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

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

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

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

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

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

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

Nicolas Wefers¹, Daniel Vlček², Wilson Heiler¹, Stephan Gabriel¹

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

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

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

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

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

Wei Zhang, Ji Wang, Weishi Peng, Jinbiao Xiong

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

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

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

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

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

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

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

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

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

Central Research Institute of Electric Power Industry, Japan

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

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

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

Spray-cooling Heat Transfer of a Hot Tank Wall

Kristian Patrik Angele

Vattenfall AB, Sweden

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

Wei Deng, Pengcheng Zhao, Tao Yu

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

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

Alexandre Guyot

EDF (Electricité de France), France

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

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

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

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

Hongkang Tian, Tenglong Cong, Hanyang Gu

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

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

Mengyan Hu, Wenxuan Wang, Zongyang Li, Jun Yang

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

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