Conference Agenda

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

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

miscibleSpeciesTransport: A New OpenFOAM-based Framework for Studying Interphase Tritium Transfer in Molten Salt Systems

Benjamin James Li, Guanyu Su

University of California Berkeley, United States of America

POD-Based Reduced Order Modeling of Molten-Salt CFD Simulations

Charlie Owen¹, Ethan Rozak¹, Kevin Clarno¹, Cole Gentry¹, Yassin Hassan², Joseph Seo²

1: University of Texas at Austin, United States of America; 2: Texas A&M University, United States of America

Conjugate Heat Transfer Analysis of the Stable Salt Reactor Fuel Pin Using Spectral Element Simulations

Jun Fang¹, Dillon Shaver¹, Ling Zou¹, Thanh Hua¹, Luke Godfrey², Rory O’Sullivan²

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

Development of Phase Transition Model a Salt Spill Behavior Analysis Using Moving Particle Semi-implcit Method

Yun Sik Cho, Ye Hwan Chun, JinHo Song, Sung Joong Kim

Hanyang Univ., Korea, Republic of

Development and Validation of Two-Phase Flow Models in MOOSE for Molten Salt Reactor Application

Mengnan Li, Mauricio Tano, Piyush Sabharwall, Joshua E. Hansel

Idaho National Laboratory, United States of America

Simulation of NACIE Benchmark Tests using NekRS

Dillon Shaver¹, Maximiliano Dalinger²

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

MultiMorph - An Euler-Euler based CFD Framework for Multiphase Flows Combining Resolved and Unresolved Structures

Fabian Schlegel, Richard Meller, Benjamin Krull, Ronald Lehnigk, Dirk Lucas

Helmholtz-Zentrum Dresden - Rossendorf (HZDR), Germany

CFD Analysis of Turbulence and Bubble Size Development in a Vertical Pipe Bubbly Flow under Partial Blockage Condition

Yixiang Liao

Helmholtz-Zentrum Dresden - Rossendorf e.V., Germany

Role of Heat Loss in CFD Simulations of Slow Hydrogen Deflagration

Julius Venckus, Mantas Povilaitis

Lithuanian Energy Institute, Lithuania

CFD Assessment of Pressure Drop in Fuel Elements, Effect of Turbulence Model, Comparison with Experiments

Jan-patrice Simoneau

EDF, France

Potential to Optimize Flow Patterns through the Core for the FRM II Conversion using CFD

Kaltrina Shehu, Ronja Schönecker, Christian Reiter

Forschungs-Neutronenquelle Heinz Meier-Leibnitz, Technical University of Munich, Germany

Development of a Coarse-grid CFD Model within the Nuclear Reactor Fuel Assembly

Jeggathishwaran Panisilvam¹, Shuisheng He¹, Bo Liu², Jean-Marie Le Corre³

1: University of Sheffield, United Kingdom; 2: Science and Technology Facilities Council (STFC), United Kingdom; 3: Westinghouse Electric Sweden AB, Sweden

CFD Study of Spacer-grid Induced Turbulence in Typical Pressurized Water Reactor

Tu Guang Tan¹, Nasr Mahmoud², Md Abdur Razzak², Sicong Xiao¹

1: Singapore Nuclear Research and Safety Initiative, Singapore; 2: Temasek Laboratories, Singapore

CFD for Nuclear Safety Studies: Challenges and Related Activities within WGAMA CFD-Task Group

Pierre Ruyer¹, Stephan Kelm², Jan-Patrice Simoneau³, Mingjun Wang⁴, Martina Adorni⁵

1: IRSN, France; 2: Forschung Zentrum Juelich, Germany; 3: EDF, France; 4: Xi'an Jiaotong University, China, People's Republic of; 5: NEA, France

Development and Applications of the Computational Fluid Dynamics Code for Nuclear Reactors-WINGS-CFD

Wei Zeng, Zonglan Wei

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

Coarse-mesh CFD Simulations of Rod Bundle Flows

Ezequiel Oscar Fogliatto, Ivor David Clifford

PSI Center for Nuclear Engineering and Sciences, Switzerland

Condition-Adaptive Anisotropic Eddy Viscosity Turbulent Model for Subchannels in Rod Bundles with Specific Mixing Vane Grid

Siwei Qi¹, Bin Han¹, Xiaoliang Zhu¹, Bao-Wen Yang², Jiahao Zhao¹

1: Southeast University, China, People's Republic of; 2: DEQD, China, People's Republic of

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

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

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

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

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

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

How to Achieve Robust CFD Acceleration with Scientific Machine Learning

Shilaj Baral¹, Sangam Khanal¹, Youngkyu Lee², Joongoo Jeon¹

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

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

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

Rolls-Royce, United Kingdom

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

Guanqun Ding, Yao Xiao, Hanyang Gu

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

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

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

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

Numerical Simulation of Aerosol Dispersion Characteristics after Nuclear Power Plant Accident

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

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

Analysis of Small Break LOCA of ACME Based on SCENES

Qichao Ma, Hao Zhang, Meng Zhao, Yanhua Yang

Shanghai JiaoTong University, China, People's Republic of

Simulating Molten Corium Concrete Interaction: A Multiphase Approach with OpenFOAM

Kamran Mahboob, Ahmed AlKaabi, Yacine Addad

Khalifa University, United Arab Emirates

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

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

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

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

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

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

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

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

Virginia Commonwealth University, United States of America

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

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

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

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

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

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

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

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

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

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

QiongTao Li, QianNi Duan, Wei Li, JunMei Wu

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

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

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

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

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

Martin Draksler, Iztok Tiselj

Jožef Stefan Institute, Slovenia

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

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

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

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

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

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