Advances in Thermal Hydraulics (ATH 2024)

Full Issue

Progress and Challenges in Multiphase CFD Method Development for Nuclear Thermal Hydraulics

E.M.A. Frederix (Nuclear Research and Consultancy Group)

Visualization and Phenomenological Modeling of Subcooled Flow Boiling

Tomio Okawa (Univ. Electro-Communications)

Some Reflections and Developments for Phenomena Identification and Scaling Analysis Applied to Thermal-Hydraulics of Nuclear Reactors

Sofia Carnevali (CEA)

Large-Scale Experiments and Simulation Benchmarks for Containment Thermal Hydraulics

Sanjeev Gupta (Becker Technologies)

Innovations in Thermal-Hydraulic Testing and Modeling of Boiling Water Reactor Fuel at Westinghouse

Jean-Marie Le Corre (Westinghouse Electric Sweden), Fredrik Waldemarsson (Westinghouse Electric Sweden), Carl Adamsson (Westinghouse Electric Sweden), Uffe Bergmann (Westinghouse Electric Sweden)

New Approaches for Multidimensional Measurement of Boiling Two-Phase Flow in Fuel Rod Bundle

Takahiro Arai (Central Research Institute of Electric Power Industry)

Modular Heat Pipes for Nuclear Applications

Robert Reid (LANL)

Performance Validation of the Passive Safety Features in Near Term PWRs in Korea

Han-Gon Kim (Innovative SMR Agency)

Making Nuclear Competitive in Future Energy Markets with Thermal Hydraulic Research

Jeong Ik Lee (KAIST)

Initial Framework Demonstration to Support High-Burnup PWR and BWR LOCA Analysis

Nathan Capps (ORNL)

Fluid-Structure Interaction Evaluation of LVDT for Deflection Measurements of MURR LEU Fuel Plate

Guanyi Wang (ANL), Cezary Bojanowski (ANL), Andrew Hebden (ANL), Walid Mohamed (ANL), Valerio Mascolino (ANL), Earl Feldman (ANL), Erik Wilson (ANL), Aaron Weiss (Oregon State), Alexander Westerberg (Oregon State), Wade Marcum (Oregon State), Maria Pinilla (Univ. Missouri Research Reactor)

Advances in Thermal Hydraulics in the Dutch PIONEER Program

F. Roelofs (Nuclear Research & Consultancy Group), B.T.H. Verdonschot (Nuclear Research & Consultancy Group), F.S.L. Pangukir (Nuclear Research & Consultancy Group), P. Breijder (Nuclear Research & Consultancy Group), M.M.M.D. Hussain (Nuclear Research & Consultancy Group), V. Habiyaremye (Nuclear Research & Consultancy Group), E. Frederix (Nuclear Research & Consultancy Group), A. Mathur (Nuclear Research & Consultancy Group), K. Zwijsen (Nuclear Research & Consultancy Group), H. Uitslag-Doolaard (Nuclear Research & Consultancy Group), D.C. Visser (Nuclear Research & Consultancy Group), M.M. Stempniewicz (Nuclear Research & Consultancy Group), E.M.J. Komen (Nuclear Research & Consultancy Group)

Thermal Fatigue -- The Influence of Frequency on Temperature Fluctuation Amplitude

K. Angele (R&D Laboratories), P. Veber (Ringhals Nuclear Power Plant), H. Lindqvist (Forsmarks Kraftgrupp AB)

Prevention of Swirl Penetration in a T-Junction Dead-Leg Flow to Mitigate a Source of Thermal Fatigue

K. Angele (R&D Laboratories), R. Howard (Electricité de France)

Development of AMESIM Code Based Safety Analysis Methodology for PGSFR

Seon-Gon Kim (Gachon Univ.), Jae-Ho Jeong (Gachon Univ.)

Numerical Simulation of Molten Salt Spreading Behavior Under the Salt Spill Accident of Molten Salt Reactor

Jun Ho Bae (KAERI), Sung Il Kim (KAERI), Hyun Seok Jang (Kyungpook Nat'l Univ.), Il Seok Park (Kyungpook Nat'l Univ.)

Numerical Investigation on Thermohydraulic Behavior of Molten Salt During Salt Spill Accident in MSR

Sang Mo An (KAERI), Sung Il Kim (KAERI)

Phenomena Identification and Ranking Table for Accident Condition of Molten Salt Reactor

Byeonghee Lee (KAERI), Sung-Il Kim (KAERI)

Three-Dimensional Simulation of Noble Metal Particle Removal Rates in the Molten Salt Fast Reactor

E.M.A. Frederix (Nuclear Research and Consultancy Group), V. Habiyaremye (Nuclear Research and Consultancy Group)

Design and Construction of a Molten Salt Latent Heat Thermal Energy Storage Validation Experiment

Trevor Casper (Univ. Idaho), David Arcilesi (Univ. Idaho), Richard Christensen (Univ. Idaho)

Method for Measuring Molten Salt HTC in Static Tubes

Luke Godfrey (Moltex FLEX), Alberto Ferreira (Moltex)

Feasibility Study on Load-Following Simulation Using SMR Innovation Platform

J.H. Seo (Ulsan Nat'l Institute Science and Technology), I.C. Bang (Ulsan Nat'l Institute Science and Technology)

Analysis of Station Blackout for the LDR-50 SMR in SPECTRA and Apros

Bart Verdonschot (Nuclear Research & Consultancy Group), Paul Breijder (Nuclear Research & Consultancy Group), Ferry Roelofs (Nuclear Research & Consultancy Group), Rebekka Komu (VTT)

Downward Reflood Quenching and the Effects of Power Distribution and Mixing Vane Spacer Grid near the Exit of Fuel Assemblies in SMRs and Other LWR Reactors

Bao-Wen Yang (DEQD Delta Energy Group New York), Jeremy Silber (DEQD Delta Energy Group New York), Stephanie H. Yang (DEQD Delta Energy Group New York), Christopher Lepore (DEQD Delta Energy Group New York), Eric Yang (Carp Assoc. USA), Bin Han (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Aiguo Liu (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer)

Scoping Analyses for the Definition of New Experiments for Natural Convection at High Rayleigh Numbers

A. Morente (EDF), J. Uribe (EDF), S. Benhamadouche (EDF), P. Rotach (EDF), J.-L. Vacher (EDF), M.S. Chae (PSI), D. Paladino (PSI)

Preliminary Thermal Margin Assessment at an External Reactor Vessel of SMR Using a System Code

Yonadan Choi (KAIST), Dong-Hun Shin (KAIST), Young Hee Kim (KAIST), Yong Hoon Jeong (KAIST)

Develop a Comprehensive Phenomena Identification and Ranking Table (PIRT) for AP300 SMR

Jun Liao (Westinghouse Electric Co.), Richard F. Wright (Westinghouse Electric Co.), Megan E. Durse (Westinghouse Electric Co.), Oriol N. Oliva (Westinghouse Electric Co.), Bryan Friedman (Westinghouse Electric Co.)

AI-Enabled Fuel Temperature Prediction with Digital Visualization Using Heat Pipes in Microreactor Monolith Cores

Ik Jae Jin (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)

Data Efficiency Assessment of Generative Adversarial Networks for Critical Heat Flux Synthetic Data Generation

Umme Mahbuba Nabila (Univ. Michigan), Linyu Lin (INL), Majdi I. Radaideh (Univ. Michigan)

Probabilistic Bayesian Neural Network (PBNN) for CHF Prediction with Uncertainty in a Uniformly Heated Vertical Tube Using CHF NRC Database

Anadi Mondal (Univ. Massachusetts, Lowell), Subash L. Sharma (Univ. Massachusetts, Lowell)

Improved Heat Transfer Modeling in a Channel Flow with Rough Surfaces Using Wall Functions

V. Habiyaremye (Nuclear Research and Consultancy Group), A Math.ur (Nuclear Research and Consultancy Group), F. Roelofs (Nuclear Research and Consultancy Group), J.W.R. Peeters (Delft Univ. Technology)

Pressure-Corrected Wall Functions for the k - τ RANS Model in Nek5000

Nadish Saini (ANL), Ananias Tomboulides (Aristotle Univ., Thessaloniki), Dillon Shaver (ANL), Aleksandr Obabko (ANL)

Numerical Investigation of Turbulent Flow Through an Orifice Plate at $Re \approx 10^6$: A RANS-Based Methodology for Predicting Discharge Coefficients with ISO 5167 Uncertainty

Pascal Borel (EDF), Sofiane Benhamadouche (EDF), Didier Boldo (EDF)

Free Surface Steam-Interface Heat Transfer Model with a Wall Function that takes Roughness into Account

Bruno Raverdy (CEA)

URANS Computations of Nakamura et al. Dead Branch Configuration -- Evaluation of the Velocity Field Predictions

Sofiane Benhamadouche (EDF)

Assessment of Physics-Informed Neural Networks (PINNs) with Transfer Learning (TL) for Incompressible Turbulent Flows

Y.H. Wong (Imperial College London), Y. Duan (Imperial College London), L. Lampunio (Imperial College London), M.D. Eaton (Imperial College London), M.J.Bluck (Imperial College London)

Prediction and Uncertainty Quantification of Critical Heat Flux -- A Comparison Between Generative Conditional VAEs and DNNs

Farah Alsafadi (NCSU), Aidan Furlong (NCSU), Xu Wu (NCSU)

Quantifying Model Uncertainty of Neural-Network Based Turbulence Closures

Cody Grogan (Utah State), Som Dutta (Utah State), Mauricio Tano (INL), Somayajulu L.N. Dhulipala (INL), Izabela Gutowska (Oregon State)

VOCAL: Validation, Optical Calibration and Learning Interactive Graphical Interface for Distributed Temperature Sensing in Advanced Reactors

Lauren Kohler (NCSU), Matthew Weathered (ANL), Alexander Heifetz (ANL)

The Use of Transfer Learning to Extend Critical Heat Flux Predictions

Aidan Furlong (NCSU), Xu Wu (NCSU)

Multi-physics Modeling of Radiative Heat Transfer and Fluid Flow for the Reactor Cavity Cooling System

Sinan Okyay (Penn State), Victor Coppo Leite (INL), Elia Merzari (Penn State), Paolo Balestra (INL), Gerhard Strydom (INL)

Development of the CNN-Based Computer Vision Method for Pressure Field Reconstruction in Turbulent Channel Flow

Congshan Mao (University of Missouri, Columbia), Yue Jin (University of Missouri, Columbia)

Nucleation Site Interactions in High-Fidelity Pool Boiling Simulations

Anna Iskhakova (NCSU), Om Jagtap (NCSU), Nam T. Dinh (NCSU), Igor A. Bolotnov (NCSU)

Turbulent to Laminar Flow Transition Study in Parallel Plate Geometry Using Direct Numerical Simulation

Alexey Burbasov (NCSU), Tri Nguyen (Penn State), Elia Merzari (Penn State), Igor A. Bolotnov (NCSU)

CFD Simulation of Flow Distribution in Molten Salt Reactor Experiment Lower Plenum

Jun Fang (ANL), Dillon Shaver (ANL), Tingzhou Fei (ANL)

Validation of DNB Prediction Capability of STAR-CCM+ Eulerian-Eulerian Multiphase Flow Model Under Inclined Conditions for Floating Nuclear Power Plant

Giwon Bae (Seoul Nat'l Univ.), Hyoung kyu Cho (Seoul Nat'l Univ.)

Computational Analysis of Molten Salt Freeze Valves with STAR-CCM+

Anutam Bairagi (Univ. New Mexico), Minghui Chen (Univ. New Mexico)

Comparing Fidelity of RANS Turbulence Closures for Modeling Buoyant Jets Under Thermal Stratification

Som Dutta (Utah State), Anton Kadomtsev (Utah State), Mauricio Tano (INL), Izabela Gutowska (Oregon State), Paul Fischer (Univ. Illinois, Urbana-Champaign)

A Dynamic Turbulence Tracking Approach for Uncertainty Quantification of URANS CFD Models

Yu-Jou Wang (MIT), Emilio Baglietto (MIT)

Eddy Viscosity Prediction and Uncertainty Quantification with Bayesian Optimized Deep Ensemble Based on Densely Connected Convolutional Networks

Zaid Abulawi (TAMU), Yang Liu (TAMU), Rui Hu (ANL)

Continuous Galerkin Spectral Element Implementation for Interface Capturing Simulation of Glass Melters in Nek5000

Nadish Saini (ANL), Dillon Shaver (ANL), Donna Guillen (INL)

Assessment of Intermediate Break Loss of Coolant Accident with TRACE code

Seung Hun Yoo (Korea Institute of Nuclear Safety), Yong Seok Choi (Korea Institute of Nuclear Safety), Sungchu Song (Korea Institute of Nuclear Safety)

Code Benchmark of a Depressurized Conduction Cooldown Transient in the High Temperature Test Facility

Robert F. Kile (INL), Aaron S. Epiney (INL), Thanh Hua (ANL), Ling Zou (ANL), Sung Nam Lee (KAERI), Geoff Waddington (Canadian Nuclear Laboratories), Xianmin Huang (Canadian Nuclear Laboratories), Tariq Jafri (Canadian Nuclear Laboratires), Fajar Pangukir (Nuclear Research and Consultancy Group), Marek Stempniewicz (Nuclear Research and Consultancy Group), Ferry Roelofs (Nuclear Research and Consultancy Group), Gustáv Mayer (HUN-REN Centre for Energy Research), Zsombor Bali (HUN-REN Centre for Energy Research)

Bond Graph Modeling Based System Scaling Analysis: Quantifying the Impact of Distortions

Marcos G. Ortiz (Information Systems Laboratories)

Progress Towards the Lower Plenum Mixing Test of the High Temperature Test Facility Benchmark by NRG and OSU

M.M.M.D. Hussain (NRG), B. Nakhnikian-Weintraub (OSU), I. Gutowska (OSU)

A Cross-Code Verification Study for Conjugate Heat Transfer in Gas-Cooled Pebble Bed Reactors

Dezhi Dai (ANL), Haomin Yuan (ANL), Prasad Vegendla (ANL), Adrian Tentner (ANL), John Acierno (Penn State), Michael Seneca (Penn State), Tri Nguyen (Penn State), Elia Merzari (Penn State)

A Numerical Test Bed on Algorithms Efficient for Advanced System Analysis Code Development

Ling Zou (ANL), Rui Hu (ANL)

Implementing a Corrosion-Oxidation Modeling Capability in SAM for Lead-Cooled Fast Reactors

Travis Mui (ANL), Thanh Hua (ANL), Ling Zou (ANL), Rui Hu (ANL), Jun Liao (Westinghouse Electric Co.)

Severe Accident Analysis of OPR-1000 Plant Using CINEMA Code

Jun-young Kang (KAERI), Donggun Son (KAERI), Jae Hyun Ham (KAERI), Yong Mann Song (KAERI), Jun Ho Bae (KAERI)

A New One-Dimensional Model for Thermal Mixing and Stratification in Reactor Applications

Eric Cervi (ANL), Ling Zou (ANL), Yeongshin Jeong (ANL), Rui Hu (ANL)

Development of A System Analysis Model to Evaluate the Conceptual Design of the Reactor Cavity Cooling System of the Horizontal Compact High Temperature Gas-Cooled Reactor (HC-HTGR)

Yeongshin Jeong (ANL), Darius Lisowski (ANL), Qiuping Lv (ANL), Rui Hu (ANL)

Simulations of Boiling Phenomena Using Adaptive PLIC-VOF Method

Dezhi Dai (ANL), Haomin Yuan (ANL), Adrian Tentner (ANL), Albert Y. Tong (Univ. Texas, Arlington)

High Resolution Temperature Measurements During a LOCA Reflood Event

Keegan D. Murray (Univ. Wisconsin, Madison), Tiago A. Moreira (Univ. Wisconsin, Madison), Mark H. Anderson (Univ. Wisconsin, Madison)

Comparison of Pool Quench and Flow Quench Temperature in Terms of Temperature Measurement Position

WooHyun Jung (Univ. Wisconsin, Madison), Cole Dunbar (Univ. Wisconsin, Madison), Nicolas Fox (Univ. Wisconsin, Madison), Thomas Demo (Univ. Wisconsin, Madison), Kumar Sridharan (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison), Hwasung Yeom (Pohang Univ. Science and Technology)

Local Surface Temperatures and Bubble Dynamics of Pool Boiling Experiments Using a Fiber Optic Sensor

Hyeonmin Choi (Gyeongsang Nat'l Univ.), Hyewon Kim (Gyeongsang Nat'l Univ.), Dong Eok Kim (Chung-Ang Univ.), Hyungmo Kim (Gyeongsang Nat'l Univ.)

Development of a Continuous Type Liquid Level Indicator Using an Optical Fiber Sensor

Hyewon Lim (Gyeongsang Nat'l Univ.), Hayeol Kim (Ulsan Nat'l Institute Science and Technology), Imdoo Jung (Ulsan Nat'l Institute Science and Technology), Hyungmo Kim (Gyeongsang Nat'l Univ.)

Reactor Vessel Cooling System for the GA-EMS Fast Modular Reactor: Scaled Experiments and Analysis

S.K. Jung (Univ. Wisconsin, Madison), I. Jentz (Univ. Wisconsin, Madison), W.H. Jung (Univ. Wisconsin, Madison), B. Lindley (Univ. Wisconsin, Madison), M. Anderson (Univ. Wisconsin, Madison), M. Corradini (Univ. Wisconsin, Madison), H. Choi (General Atomics), J. Bolin (General Atomics)

Development of an Improved RELAP5-3D Model for the High Temperature Test Facility

Robert F. Kile (INL), Aaron S. Epiney (INL)

Effects of Upper Chimney Throttling on Two-Phase Flow in a Large-Scale Water-Based RCCS

Matthew J. Jasica (ANL), Qiuping Lv (ANL), Darius D. Lisowski (ANL), Mitch Farmer (ANL)

Effect of Water Tank Inlet Elevation on Performance of a Large Scale Water-Based RCCS

Qiuping Lv (ANL), Matthew Jasica (ANL), Darius Lisowski (ANL), Zhiee Jhia Ooi (ANL), Rui Hu (ANL), Mitch Farmer (ANL)

Contact Thermal Resistance Modeling for Conjugate Heat Transfer Simulations in Gas-Cooled Pebble Bed Reactors

Dezhi Dai (ANL), Haomin Yuan (ANL), Prasad Vegendla (ANL), Adrian Tentner (ANL)

Relative Velocity in Horizontal Bubbly Two-Phase Flows: Experiments and Modeling

Adam Dix (Purdue Univ.), Seungjin Kim (Purdue Univ.)

Experimental Study of Air-Water Two-Phase Flow Across a Vertical U-bend

Zhengting Quan (Purdue Univ.), Alicja Stoppel (Purdue University Student Section), Adam Dix (Purdue Univ.), Seungjin Kim (Purdue Univ.)

Experimental Study of Two-Phase Flow Pressure Drop Across a U-bend and Evaluation of Existing Correlations

Alicja Stoppel (Purdue Univ.), Zhengting Quan (Purdue Univ.), Seungjin Kim (Purdue Univ.)

A Direct Comparison of RGB Flow Pattern Mapping of Impedance Meter Signals with Flow Visualization

David Kang (Purdue Univ.), Seungjin Kim (Purdue Univ.)

Steam Flow Simulation Through the Swirler Section of a Steam Separator

Taylor Grubbs (NCSU), Igor Bolotnov (NCSU)

Preliminary Experiment on Local Hot Spots in Liquid Metal Cooled Wire-wrapped Pin Bundles

Taehwan Ahn (ETH Zurich), Victor Petrov (ETH Zürich), Annalisa Manera (ETH Zürich), Wilhelm-Martin Bissels (PSI)

Code Comparison of SE2ANL and DASSH Using a Medium-Size SFR

Michael A. Smith (ANL), Kyle Ramey (ANL), Nicolas Stauff (ANL)

Modeling of Natural Convection in Low Prandtl Number Fluids Using a Novel Local Algebraic Heat Flux Model

Victor Habiyaremye (Nuclear Research and Consultancy Group), Akshat Mathur (Nuclear Research and Consultancy Group), Ferry Roelofs (Nuclear Research and Consultancy Group)

Coupling SAS-FATE for Mechanistic Source Term Analysis of Lead-Cooled Fast Reactors

Sung Jin Lee (Fauske & Assoc.), Luciano Maniaci (Westinghouse Electric Co.), Jim Scobel (Westinghouse Electric Co.), Jun Liao (Westinghouse Electric Co.), Paolo Ferroni (Westinghouse Electric Co.), Dan O’Grady (ANL)

Experimental Friction Factor for Wire-Wrapped Bundle with a Porous Blockage

Matthew Kinsky (TAMU), Dalton Pyle (TAMU), Craig Menezes (TAMU), Yassin Hassan (TAMU)

Numerical Study on Sodium Heat Transfer Characteristics for PLANDTL 37-Pin Fuel Assembly

Won-Seok Ryoo (Gachon Univ.), Gi-Uk Choi (Gachon Univ.), Jae-Ho Jeong (Gachon Univ.)

Multi-physics Simulation of a Reference Fluoride-Salt-Cooled High-Temperature Reactor with Coupled SAM/Griffin

Gang Yang (ANL), Ling Zou (ANL), Rui Hu (ANL), Zhiee Jhia Ooi (ANL), Travis Mui (ANL), Javier Ortensi (INL), Joshua Hanophy (INL)

Application of Real-Time Hybrid Simulation to Nuclear Thermal Hydraulics Testing

Austin M. Warren (Oregon State), Trevor K. Howard (Oregon State)

Dry-Out Limit Investigation and Methodology for Determining the Optimal Charging Amount of Sodium Heat Pipes

Dong Hun Lee (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)

Preliminary Pin-Wise Multi-Physics Simulation Using CUPID Subchannel Module Coupled with Neutron Kinetics Code and Fuel Performance Code

Yeonghun Lee (Seoul Nat'l Univ.), Kyuseok Sim (Seoul Nat'l Univ.), Youho Lee (Seoul Nat'l Univ.), Jae Ryong Lee (KAERI), Hyoung Kyu Cho (Seoul Nat'l Univ.)

Preliminary Test of the Single Heat Pipe Experimental Facility with Azimuthally Asymmetric Condition

San Lee (Seoul Nat'l Univ.), Myeong Jin Jeong (Seoul Nat'l Univ.), Ye Sung Kim (Seoul Nat'l Univ.), Hyeong Kyu Cho (Seoul Nat'l Univ.)

Design and Evaluation of a Sodium Loop Heat Pipe

Hyewon Kim (Gyeongsang Nat'l Univ.), Hyeonmin Choi (Gyeongsang Nat'l Univ.), Byung Ha Park (KAERI), Hyungmo Kim (Gyeongsang Nat'l Univ.)