20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Full Issue

Subchannel Methods Development for Modeling of Light-Water Reactors at Oak Ridge National Laboratory

Robert Salko (ORNL), Belgacem Hizoum (ORNL), Vineet Kumar (ORNL), Aaron Wysocki, (ORNL), Aaron Graham (ORNL), David Kropaczek (ORNL), Mehdi Asgari (ORNL), Agustin Abarca (NCSU), Maria Avramova (NCSU), Benjamin Collins (Veracity Nuclear)

High-Fidelity Multiphysics for Fission: Challenges, Accomplishments, and Future Directions

A.J. Novak (ANL), P. Shriwise (ANL), P. Romano (ANL), D. Shaver (ANL), J. Fang (ANL), H. Yuan (ANL), D. Gaston (INL), E. Merzari (Penn State), H. Brooks (United Kingdom Atomic Energy Authority), A. Huxford (Univ. Michigan)

Recent Progress in Boiling Flow Simulation Using Interface Tracking Method

Y. Sato (Paul Scherrer Institute)

Implementation of a Three-Field Framework in TRACE to Improve the Prediction of Reactor Core Reflood Conditions Part I

Matthew Bernard (U.S. Nuclear Regulatory Commission), Stephen Bajorek (U.S. Nuclear Regulatory Commission)

Implementation of a Three-Field Framework in TRACE to Improve the Prediction of Reactor Core Reflood Conditions Part II

Omar S. Al-Yahia (Paul Scherrer Institute), Matthew Bernard (U.S. Nuclear Regulatory Commission), Ivor Clifford (Paul Scherrer Institute), Gregory Perret (Paul Scherrer Institute), Stephen Bajorek (U.S. Nuclear Regulatory Commission), Hakim Ferroukhi (Paul Scherrer Institute)

Analysis of a Selected Experiment of the OSU-MASLWR Test Facility Regarding the Heat Transfer in Helically Coiled Steam Generators Using AC²-ATHLET

Julia Krieger (Ruhr-Universität Bochum), Christoph Bratfisch (Ruhr-Universität Bochum), Marco K. Koch (Ruhr-Universität Bochum)

Numerical Evaluation of the Thermal-Hydraulic Effect due to the Thermal Expansion Behavior of Fuel Subassembly

Liancheng Guo (GRS), Armin Seubert (GRS), Philipp Schöffel (GRS)

CFD Simulations of Flow Mixing Phenomenon in a Gas-Cooled Reactor Outlet Plenum

Jun Fang (ANL), Thanh Hua (ANL), Zhiee Jhia Ooi (ANL), Ling Zou (ANL)

Comparison of Sodium Stratification in CFD to Experimental Data from the Thermal Hydraulic Experimental Test Article

James McCay (Oklo), Olorunsola Akinsulire (Oklo), Isaac Dabkowski (Oklo Inc.), Pat Everett (Oklo Inc.), Matthew Weathered (ANL), Dan O'Grady (ANL), Lander Ibarra (ANL), Christopher Grandy (ANL)

CFD Simulations of the Molten Salt Fast Reactor

François Martin (CEA), Guillaume Campioni (CEA), André Bergeron (CEA), Yannick Gorsse (CEA), Elsa Merle (CNRS), Antoine Gerschenfeld (CEA)

Large Eddy Simulations of Hot Helium Issued into Cold Ambient Relevant to Pipe-Break Accident of High-Temperature Gas-Cooled Reactors (HTGRs)

Jundi He (Univ. Sheffield), Bo Liu (Science and Technology Facilities Council), Shuisheng He (Univ. Sheffield)

CFD Study of a Helium Jet and Resulting Gas Mixing in a Model HTGR Cavity

B. Liu (STFC Daresbury Laboratory), J. He (Univ. Sheffield), S. He (Univ. Sheffield), C. Moulinec (STFC Daresbury Laboratory), J. Uribe (EDF Energy)

Impact of Population Balance Model on Subcooled Flow Boiling Simulation

Daniel Vlček (Czech Technical Univ.), Yohei Sato (Paul Scherrer Institute)

Building a Boiling-Flow Multiphase CFD Framework for Nuclear Reactor Conditions

Corentin Reiss (CEA), Antoine Gerschenfeld (CEA), Catherine Colin (IMFT)

Two-Phase Modeling of Wall and Bulk Condensation by Hybrid VOF-Mixture Approach for Containment Applications

Allen George (Forschungszentrum Jülich), Stephan Kelm (Forschungszentrum Jülich), Xu Cheng (Karlsruhe Institute for Technology)

A 2D Lattice Boltzmann Model for Simulation of Single Bubble Nucleation and Departure in Pool Boiling

Guanchen Liu (Univ. Luxembourg), Filip Janasz (Univ. Luxembourg), Stephan Leyer (Univ. Luxembourg)

Investigation of Water and Helium-Cooled Decay Heat Removal Systems in a Gas-Cooled Fast Reactor

Gusztáv Mayer (Centre for Energy Research), Attila Guba (Centre for Energy Research)

LTO Modifications to Reduce the PTS Issue -- Results of TH Calculations in the Context of the APAL European Project

Markku Puustinen (LUT Univ.), Giteshkumar Patel (LUT Univ.), Pavel Kral (Nuclear Research Institute Rez), Tomas Nikl (Nuclear Research Institute Rez), Ivor Clifford (Paul Scherrer Institute), Richard Trewin (Framatome), Jürgen Hartung (GRS), Inés Mateos Canals (GRS), Andrej Prošek (Jožef Stefan Institute), Lukasz Sokolowski (Kiwa Technical Consulting), Piotr Mazgaj (Warsaw Univ. Technology), Maksym Vyshemirskyi (SSTC NRS)

Code Validation of SAM Using Forced and Natural-Circulation Data from NACIE-UP Benchmark

Victor Coppo Leite (Penn State), Elia Merzari (Penn State), Adam Dix (Purdue), Ling Zou (ANL)

Recent RELAP5-3D Developments for Water and Gas-Cooled Reactors

George L. Mesina (INL), Robert P. Martin (BWX Technologies)

Modelling and Optimization of Free-Piston Stirling Engine Generators for Microreactor Applications Using SAGE Software

Phat Doan (Univ. New Mexico), Minghui Chen (Univ. New Mexico)

2-D URANS Simulation of Liquid Metal Crossflow in Tube Bundle Using Algebraic Heat Flux Model

Namhyeong Kim (Pohang Univ. Science and Technology), Jae Hyun Choi (Pohang Univ. Science and Technology), Seong Min Shin (Pohang Univ. Science and Technology), Su Won Lee (Pohang Univ. Science and Technology), HangJin Jo (Pohang Univ. Science and Technology)

LES and RANS Modeling of an 84-pin Hexagonal Rod Bundle with Spacer Grid

Adam R. Kraus (Penn State), Elia Merzari (Penn State)

Evaluation of RANS vs. LES Simulation of Fluid Flow Through 3x3 Rod Bundle with a Simple Spacer Grid as a Precursor to Coupled Fluid-Structure Interaction Simulations

Landon Brockmeyer (ANL), Nadish Saini (ANL), Adrian Tentner (ANL), Elia Merzari (Penn State)

Coupled RANS Simulation of Sodium-Cooled Fast Reactor Components Using the Spectral Element Code Nek5000

Nadish Saini (ANL), Haomin Yuan (ANL), Dillon Shaver (ANL)

Large Eddy Simulation of a 61-Pin Wire-Wrapped Bundle with a Localized Blockage

Octavio Bovati (TAMU), Yassin A. Hassan (TAMU)

CFD Evaluation of Spacer Induced Droplet Deposition in BWR Subchannels

Chao Wang (Framatome), Steven Anderson (Framatome), Markus Rehm (Framatome), Olga Dutkiewicz (Framatome), Elmar Rieder (Framatome), Lukas Robers (Axpo Power AG)

Numerical Simulation of Corium Flow Through Rod Bundle and/or Debris Bed Geometries with a Model Based on Lattice Boltzmann Method

J. Garcia Sarmiento (IRSN), F. Fichot (IRSN), V. Topin (IRSN), P. Sagaut (Aix-Marseille Univ.)

Prediction of the Flow Patterns in a Steam Generator Tube Bundle Configuration with All-Flow-Regime CFD Models

Marco Colombo (Univ. Sheffield), Daniele Vivaldi (IRSN), Jean Baccou (IRSN)

Numerical Investigation of Two-Phase Flow in a 3 x 3 Rod Bundle with Spacer Grid

S. Taş (Helmholtz-Zentrum Dresden-Rossendorf), Y. Liao (Helmholtz Zentrum-Dresden Rossendorf), U. Hampel (Helmholtz Zentrum-Dresden Rossendorf)

Development of Solids Transport Model for Fuel Dispersal Studies

Avinash Moharana (Rensselaer Polytechnic Institute), Shanbin Shi (Rensselaer Polytechnic Institute)

Nek5000-Pronghorn-SAM Multiscale Modeling of Pool-Type Molten Salt Reactors

M. Tano (INL), S. Walker (INL), A. Abou-Jaoude (INL), J. Fang (ANL), D. Shaver (ANL)

Development and First Applications of the Multi-Scale Multi-Physics Platform myMUSCLE -- MUSCLE-Foam

F. Roelofs (Nuclear Research & Consultancy Group), K. Zwijsen (Nuclear Research & Consultancy Group), H. J. Uitslag-Doolaard (Nuclear Research & Consultancy Group), V. Habiyaremye (Nuclear Research & Consultancy Group), E. Cervi (Nuclear Research & Consultancy Group), M. Stempniewicz (Nuclear Research & Consultancy Group)

Two-Phase Coupled 1D-3D ATHLET -- OpenFOAM Calculations of the OECD/NEA Large Scale Test Facility ROSA V Test 1.1

Z. Yang (GRS), J. Herb (GRS), A. Papukchiev (GRS)

Validation of SAM-NekRS Coupling Against the TALL-3D STH/CFD Coupling Benchmark Transient

A. Huxford (Univ. Michigan), V. Coppo Leite (Penn State), E. Merzari (Penn State), L. Zou (ANL), V. Petrov (Univ. Michigan), A. Manera (ETH Zürich)

Trace Code Reflood Thermal-Hydraulics Benchmarking Against the NRC-PSU Rod Bundle Heat Transfer (RBHT) Test Facility

Grant R. Garrett (Penn State), Douglas J. Miller (Penn State), Turki Almudhhi (Penn State), Fan-Bill Cheung (Penn State), Brian R. Lowery (ARL), Molly K. Hanson (ARL), Stephen M. Bajorek (NRC), Kirk Tien (NRC), Chris L. Hoxie (NRC)

SBLOCA Analysis of Floating Nuclear Reactor Under Ocean Condition Using MARS-KS Moving Reactor Model

Yujoeng Ko (Seoul Nat'l Univ.), Hyungjoo Seo (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.), Han Rim Choi (KEPCO-ENC)

Implementation of the Homogeneous Equilibrium Model (HEM) into the SAM Code for Two-Phase Flow Modeling

Michael Gorman (TAMU), Ling Zou (ANL), Rui Hu (ANL), Yassin A. Hassan (TAMU)

Core Damage Extent Analysis of Large-Break LOCA for 4-Loop Pressurized Water Reactor with Detailed 3D Model of Reactor Pressure Vessel and Core

Matthias Jobst (Helmholtz-Zentrum Dresden-Rossendorf), Eduard Diaz-Pescador (Helmholtz-Zentrum Dresden-Rossendorf), Sören Kliem (Helmholtz-Zentrum Dresden-Rossendorf)

Research on Accelerated Methods for Three-Dimensional Nuclear System Analysis Programs

Ge Li (Xi’an Jiaotong Univ.), Li Huaqi (Northwest Institute of Nuclear Technology), Shan Jianqiang (Xi’an Jiaotong Univ.)

CFD Simulations of the UPTF-TRAM Test C1

E. Fogliatto (Paul Scherrer Institute), I. Clifford (Paul Scherrer Institute)

CFD Simulations of Large-Scale Tests Highlighting the Effects of Thermal Radiation in Steam-Containing Atmospheres

A. Dehbi (Paul Scherrer Institute), R. Kapulla (Paul Scherrer Institute)

Assessment of Neptune_CFD Applied to the Study of a Passive Safety Condenser: Modeling and First Validation Elements

Jorge Perez (CEA), Bruno Raverdy (CEA), Clément Liegeard (CEA), Franck Morin (CEA), Nicolas Merigoux (EDF), Jérôme Lavieville (EDF), Chaï Koren (EDF), Nicolas Sobecki (EDF), Michael Montout (EDF), Thomas Prusek (EDF), Pierre Gaillard (Framatome)

High-Fidelity CFD Simulation of Mixed Convection in a Pebble Bed Test Reactor Core

Haomin Yuan (ANL), Dillon Shaver (ANL), Tri Nguyen (Penn State), Elia Merzari (Penn State), David Reger (Penn State), Ka-Yen Yau (Kairos Power), Giacomo Busco (Kairos Power), Nate Salpeter (Kairos Power), R. Brian Jackson (Kairos Power)

A Numerical Study of Melt Penetration into a Particulate Bed

Liang Chen (Royal Institute of Technology), Andrei Komlev (Royal Institute of Technology), Weimin Ma (Royal Institute of Technology), Sevostian Bechta (Royal Institute of Technology)

Mesoscopic Flow Boiling Simulation of a Hypervapotron Cooling Channel for Fusion Application

Hoongyo Oh (Pohang Univ. Science and Technology), HangJin Jo (Pohang Univ. Science and Technology)

Sloshing in Cylindrical Tanks: Assessment of CFD OpenFOAM Two-Phase Models Accuracy

A. Cantiani (von Karman Institute for Fluid Dynamics), J. Muller (von Karman Institute for Fluid Dynamics), L. Koloszar (von Karman Institute for Fluid Dynamics), P. Planquart (von Karman Institute for Fluid Dynamics)

Numerical Transfer Towards Unresolved Morphology Representation in the MultiMorph Model

Richard Meller (Helmholtz-Zentrum Dresden-Rossendorf), Benjamin Krull (Helmholtz-Zentrum Dresden-Rossendorf), Fabian Schlegel (Helmholtz-Zentrum Dresden-Rossendorf), Matej Tekavčič (Jožef Stefan Institute)

CFD Simulations of a LOCA Scenario for a Containment Building

Stephane Mimouni (EDF R&D), Ayouba Fofana (EDF R&D)

Modeling of Table Top Primary Heat Exchanger Experiment RUN#5 by Means of the System Codes RELAP5 MOD 3.3 and Flownex SE 8.4

D. Rozzia (SCK CEN), M. Potgieter (SCK CEN), J. Cools (SCK CEN), T. Van Loy (SCK CEN), G. Kennedy (SCK CEN), J. Pacio (SCK CEN), K. Van Tichelen (SCK CEN), R. Fernandez (SCK CEN)

Transient Quench Model for Top and Bottom Flooding of Debris Beds with Non-Condensable Gas

Abinson Paul Nedumparambil (Institute of Nuclear Technology and Energy Systems), Markus Petroff (Institute of Nuclear Technology and Energy Systems), Michael Buck (Institute of Nuclear Technology and Energy Systems), Jörg Starflinger (Institute of Nuclear Technology and Energy Systems)

Development and Verification of the Model for Supercritical Carbon Dioxide Closed Brayton Cycle System in the Reactor System Analysis Code RESYS

Zongyun Wu (China Institute of Atomic Energy), Mingyu Wu (China Institute of Atomic Energy), Tiancai Liu (China Institute of Atomic Energy)

Best-Estimate-Plus-Uncertainty Analyses of PTS Using a Mixing-Analysis Program for the APAL European Project

Richard Trewin (Framatome), Pavel Kral (Nuclear Research Institute Rez), Tomas Nikl (Nuclear Research Institute Rez)

A Lumped-Parameter Model of a Pool Heated from Below with Gravity-Driven Flashing Occurence

Jimmy Martin (IRSN), Pierre Ruyer (IRSN), Matthieu Duponcheel (Universite Catholique de Louvain), Yann Bartosiewicz (Universite Catholique de Louvain)

A Turbulence Model Sensitivity Analysis on the Hydraulic Behavior in the Inlet Plenum of the Proposed NIST Neutron Source Design

Abdullah G. Weiss (National Institute of Standards and Technology), Joy S. Shen (National Institute of Standards and Technology), Anil Gurgen (National Institute of Standards and Technology)

Development and Validation of Pattern Recognition Algorithm and Suppression Pool Flow Modelling

Giteshkumar Patel (LUT Univ.), Markku Puustinen (LUT Univ.), Juhani Hyvärinen (LUT Univ.), Elina Hujala (Université de Fribourg), Vesa Tanskanen (Stressfield Oy)

Parametric Analysis of Flame Acceleration and Quenching Simulation with flameFoam

M. Povilaitis (Lithuania Energy Institute), J. Venckus (Lithuanian Energy Institute)

Analysis of the Anisotropic Term in the Implicit Algebraic Heat Flux Model in the Case of Low Prandtl Flow in Planar Impinging Jet Case

J. Oder (von Karman Institute for Fluid Dynamics), A. Coëpeau (von Karman Institute for Fluid Dynamics), L. Koloszar (von Karman Institute for Fluid Dynamics), D. Laboureur (von Karman Institute for Fluid Dynamics), S. Keijers (SCK CEN)

Thermophoretic Particle Deposition: A Computational Fluid Dynamics Approach for Estimating Hotspots

Erdal Ozdemir (Univ. Tokyo), Shuichiro Miwa (Univ. Tokyo), Marco Pellegrini (Univ. Tokyo), Shunichi Suzuki (Univ. Tokyo), Koji Okamoto (Univ. Tokyo)

Capture the Morphology Transfer Process in a Pool-Scrubbing Column with a Hybrid Multi-Field Two-Fluid Model

Yixiang Liao (Helmholtz-Zentrum Dresden-Rossendorf), Shiwang Li (Helmholtz-Zentrum Dresden-Rossendorf)

Three-Dimensional Multiphase CFD Simulation of a Thin Liquid Film Flowing Down an Inclined Plate

Y. Rivera (UPV), M. Grasso (ETH Zürich), V. Petrov (Univ. Michigan), A. Manera (ETH Zürich)

Flow Regime Scaling Study Aided by CFD for Large Diameter High Void Fraction Systems

Brandon Aranda (MIT), Koroush Shirvan (MIT), Emilio Baglietto (MIT)

Large-Scale Multiphysics Simulations of Small Modular Reactors Operating in Natural Circulation

Jun Fang (ANL), Dillon Shaver (ANL), Paul Romano (ANL), Elia Merzari (Penn State)

Thermal Hydraulic Analysis of a SFR Fuel Assembly with Cladding Oval-Distortion Using CFD

Yaodi Li (North China Electric Power Univ.), Mei Huang (North China Electric Power Univ.), Boxue Wang (North China Electric Power Univ.)

Heat Transfer Enhancement of Supercritical Carbon Dioxide and Liquid Lead Bismuth Eutectic Compact Heat Exchanger

Shuhan Liu (Xi’an Jiaotong Univ.), Ji'an Liu (Xi’an Jiaotong Univ.), Qingjiang Liu (Xi’an Jiaotong Univ.), Xianliang Lei (Xi’an Jiaotong Univ.)

Validation Practices of Multi-Physics Core Performance Analysis in an Advanced Reactor Design Study

Norihiro Doda (Japan Atomic Energy Agency), Shinya Kato (Japan Atomic Energy Agency), Erina Hamase (Japan Atomic Energy Agency), Kazuki Kuwagaki (Japan Atomic Energy Agency), Norihiro Kikuchi (Japan Atomic Energy Agency), Kazuya Ohgama (Japan Atomic Energy Agency), Kazuo Yoshimura (Japan Atomic Energy Agency), Ryuji Yoshikawa (Japan Atomic Energy Agency), Kenji Yokoyama (Japan Atomic Energy Agency), Tomoyuki Uwaba (Japan Atomic Energy Agency), Masaaki Tanaka (Japan Atomic Energy Agency)

Pin-Wise Fuel Behavior of Nuclear Reactor Using Multi-Scale and Multi-Physics Methodology

Jae Ryong Lee (KAERI), Han Young Yoon (KAERI)

Scaled Experiment Design for Transient Coupled CFD-Reactor Physics Model for HENRI

A. Warren (Oregon State), G. Mignot (Oregon State), W. Marcum (Oregon State)

Numerical Simulation of Vibrating Rods in a Cross Flow in the Frame of an OECD Benchmark

Jan-Patrice Simoneau (EDF)

Influence of Relative Power Difference Weighting on Convergence of Coupled Neutronic Thermal-Hydraulic Calculations of Heavy Water Small Modular Reactor

T. Korinek (Czech Technical Univ. Prague), R. Skoda (Czech Technical Univ. Prague), M. Lovecky (Univ. West Bohemia), J. Zavorka (Univ. West Bohemia)

Simulation of the CRUD Effect in Subcooled Nucleate Boiling Area in the Subchannels of the 7 x 7 Nuclear Fuel Assembly

Hyeon Ji Kim (Ulsan Nat'l Institute Science and Technology), Ji Yong Kim (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)

Development of Wall Heat Flux Partitioning Model for Subcooled Flow Boiling Based on CFD

Shihao Yang (Beijing Jiaotong Univ.), Bo Ren (Beijing Jiaotong Univ.), Lixin Yang (Beijing Jiaotong Univ.)

Comparison of CFD Simulations and Porous Media Simulations of a Gas-Cooled Pebble Bed Core Under Forced and Mixed Convection Conditions

Dezhi Dai (ANL), Prasad Vegendla (ANL), Haomin Yuan (ANL), Landon Brockmeyer (ANL), Adam Kraus (ANL), Adrian Tentner (ANL), David Reger (Penn State)

Simulation of Mixed Convection Heat Transfer to Liquid Metals in Vertical Channels and Pipes

Milorad B. Dzodzo (Westinghouse Electric Co.)

Multi-Scale Coupling of TRACE and SubChanFlow (SCF) in the SALOME Platform Using the Domain Decomposition (DD) Method and a Conservative Data Transfer Approach

Kanglong Zhang (Karlsruhe Institute of Technology), Victor Hugo Sanchez-Espinoza (Karlsruhe Institute for Technology)

Lateral Turbulent Mixing in Narrow Rectangular Channels

Basar Ozar (ANL), Jeremy R. Licht (ANL), Francesc Puig (ANL), Mohammad Kalimullah (ANL), Aurelien Bergeron (ANL)

New Developments of Subchannel CFD for Mixed Convection in Bare and Wire-Wrapped Rod Bundles Under Supercritical Pressure Conditions

C. Zhang (Univ. Sheffield), S. He (Univ. Sheffield), B. Liu (Daresbury Laboratory)

Comparative Thermal Performance of Downdraft and Updraft Forced Convection in a Representative 3x3 PWR Fuel Assembly

Vivek M. Rao (ORNL), Joseph D. Smith (Missouri Univ. Science and Technology)

CHF Prediction During an RIA with a BISON and THM Coupled Model

L. C. Aldeia Machado (Penn State), E. Merzari (Penn State), W. Walters (Penn State), L. Charlot (INL)

Analysis of the Scaling Between Model Experimental Facilities MYRRHABELLE and E-SCAPE and the MYRRHA Reactor Augmented by CFD

L. Koloszar (von Karman Institute for Fluid Dynamics), S. Lopes (von Karman Institute for Fluid Dynamics), M. Faruoli (von Karman Institute for Fluid Dynamics), Ph. Planquart (von Karman Institute for Fluid Dynamics), K. Van Tichelen (SCK CEN), J. Pacio (SCK CEN), S. Keijers (SCK CEN)

Development of Lagrangian Particle Method for Temperature Distribution Formed by Sodium-Water Reaction in a Tube Bundle System

Wataru Kosaka (Japan Atomic Energy Agency), Akihiro Uchibori (Japan Atomic Energy Agency), Yasushi Okano (Japan Atomic Energy Agency), Hideki Yanagisawa (NESI Corporation)

Validation and Comparison of HI-STORM Overpack Thermal-Hydraulic Model with MOOSE and NekRS

Sinan Okyay (Penn State), Elia Merzari (Penn State), David A. Reger (Penn State), Victor Coppo Leite (Penn State), Guillaume Giudicelli (INL), Peter German (INL), Alexander Lindsay (INL)

Unipolar Charge Injection Induced Melting Rate Enhancement in a Cylindrical Thermal Energy Storage Unit

R. Deepak Selvakumar (Khalifa Univ.), Ahmed K. Alkaabi (Khalifa Univ.)

Quantifying HFIR Turbulence by Variable Curvature Channels

Nicholas J. Mecham (NCSU), Igor A. Bolotnov (NCSU), Emilian L. Popov (ORNL)

Direct Numerical Simulation of Flow in a Confined Differentially Heated Cavity at Low Prandtl Numbers

J. Oder (von Karman Institute for Fluid Dynamics), M. Alsailani (von Karman Institute for Fluid Dynamics), L. Koloszar (von Karman Institute for Fluid Dynamics), W. Munters (von Karman Institute of Fluid Dynamics), D. Laboureur (von Karman Institute for Fluid Dynamics), J. Pacio (SCK CEN)

Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in a Simultaneously Cooled Vertical Channel

Cheng-Kai Tai (NCSU), Tri Nguyen (Penn State), Elia Merzari (Penn State), Igor A. Bolotnov (NCSU)

High Fidelity Simulation of the Light-to-Dense Stratification Transient in the HiRJET Facility

Cheng-Kai Tai (NCSU), Haomin Yuan (ANL), Elia Merzari (Penn State), Igor A. Bolotnov (NCSU)

Large-Eddy Simulation of Mixed Convection Flows in a Rod Bundle: Investigation of an Up-Scaling Methodology from CFD to Subchannel Code Validation

Vladimir Duffal (EDF R&D), Pierre-Victor Marquet (EDF R&D), Erwan Le Coupanec (EDF R&D), Stéphane Pujet (EDF R&D)

Application Study of Adaptive Mesh Refinement Method on Unsteady Wake Vortex Analysis

Haneen Alzahrani (Tokai Univ.), Takaaki Sakai (Tokai Univ.), Kentaro Matsushita (Japan Atomic Energy Agency), Toshiki Ezure (Japan Atomic Energy Agency), Masaaki Tanaka (Japan Atomic Energy Agency)

CFD Simulations of the Step Height Effects on Heat Transfer for a Turbulent Wall Jet Flow in an Unconfined Backward Facing Step Configuration

H. Ouldrebai (Univ. Sciences and Technology Houari Boumediene), Y. Halouane (Université de Boumerdes), A. Dehbi (Paul Scherrer Institute)

Full-Core Computational Fluid Dynamics Simulations Using NekRS

Dillon Shaver (ANL), Jun Fang (ANL), Haomin Yuan (ANL), Misun Min (ANL), Elia Merzari (Penn State), Yu-Hsiang Lan (Univ. Illinois, Urbana-Champaign)

CFD Modelling of Film Condensation from a Steam-Air Mixture in Vertical Channels

Bronwyn Rempel (Univ. Manitoba), Geoffrey S. Gray (Univ. Manitoba), Scott J. Ormiston (Univ. Manitoba)

CFD Modelling of Aerosol Transport and Deposition Using a Drift-Flux Model

P. Madhan Kumar (Univ. Manitoba), Geoffrey S. Gray (Univ. Manitoba), Scott J. Ormiston (Univ. Manitoba)

On the Impact of Prandtl Number on Temperature in Parallel Jet Mixing

John Acierno (Penn State), Elia Merzari (Penn State)

CFD Modeling of Gas-Liquid Vertical Up-Ward Annular Flow with Thin Liquid Film

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

Numerical Investigate on the Effects of Obstacles and Spatial Scale Changes on Hydrogen Combustion Characteristics

Tongyu Wu (Harbin Engineering Univ.), Jianfa Li (China Nuclear Power Engineering Co.), Tongyu Zhang (Harbin Engineering Univ.), Xinyan Liu (Harbin Engineering Univ.), Feng Liu (Harbin Engineering Univ.), Haozhi Bian (Harbin Engineering Univ.)

Multiscale Approach for Boiling Flow Simulation

Wei Ding (HZDR), Jinming Zhang (HZDR), Hamed Setoodeh (HZDR), Dirk Lucas (HZDR), Uwe Hampel (HZDR/TU Dresden)

Thermal-Hydraulic Assessment of the Proposed NIST Neutron Source Design

Anil Gurgen (National Institute of Standards and Technology), Abdullah G. Weiss (National Institute of Standards and Technology), Joy S. Shen (National Institute of Standards and Technology)

Analysis of Flow Blockage for the Fuel Assembly in Lead-Cooled Fast Reactor and Comparison of Analysis According to the Changed Assembly Design

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

Effect of Inner Wall Cracking on the Cavitation Bubble Formation in the Mercury Spallation Target at J-PARC

Gen Ariyoshi (Japan Atomic Energy Agency), Koichi Saruta (Japan Atomic Energy Agency), Hiroyuki Kogawa (Japan Atomic Energy Agency), Masatoshi Futakawa (Japan Atomic Energy Agency), Kohki Maeno (Ibaraki Univ.), Yanrong Li (Ibaraki Univ.), Kihei Tsutsui (Lancemore Co.)

Transient Rod Temperature Distribution Measurement Using Optical Fiber Sensor in Rod Bundle at High Pressure and Temperature

Takahiro Arai (Central Research Institute of Electric Power Industry), Riichiro Okawa (Central Research Institute of Electric Power Industry), Atsushi Ui (Central Research Institute of Electric Power Industry), Masahiro Furuya (Central Research Institute of Electric Power Industry), Tsugumasa Iiyama (Central Research Institute of Electric Power Industry), Shota Ueda (Central Research Institute of Electric Power Industry), Kenetsu Shirakawa (Central Research Institute of Electric Power Industry)

Experimental Method for Measurement of Density and Viscosity of High Temperature Heat Transfer Fluid

Jiaqi Chen (Univ. Illinois, Urbana-Champaign), C. S. Brooks (Univ. Illinois, Urbana-Champaign)

RGB Mapping: A Dynamic Approach for Flow Pattern Identification and Classification

David Kang (Purdue), Drew Ryan (Purdue), Seungjin Kim (Purdue)

Local Two-Phase Characterization of a Large-Scale RCCS Operating Under Loss of Forced Cooling Conditions

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

Design and Construction of the Experiment Facility for the High-Temperature Steam Generation with Helium for 30kW High-Temperature Steam Electrolysis

S.-Y. Kim (KAERI), S. D. Hong (KAERI), B. H. Park (KAERI), K. J. Kang (KAERI), H. S. Kim (KAERI), C. S. Kim (KAERI)

Experiments on Passive Heat Removal of Immersed Containments by Laminar and Turbulent Convection at very high Rayleigh Numbers

Martin Freitag (Becker Technologies), Eike W. Schmidt (Becker Technologies), Benjamin von Laufenberg (Becker Technologies), Sanjeev Gupta (Becker Technologies)

Recommendations for new Experiments able to Better Characterize Flashing Flows in Nozzles for Improving Critical Flow Modelling in System Codes

D. Bestion (Consultant), F. D'Auria (Univ. Pisa), K. Umminger (Framatome), P. Fillion (CEA), Seok Kim (KAERI), S. Gupta (Becker-Technologies), Uwe Hampel (Helmholtz-Zentrum Dresden-Rossendorf), Lauri Pyy (LUT Univ.), Giteshkumar Patel (LUT Univ.)

Experimental Velocity Profile Reconstruction in Thin Water Films

M. Grasso (ETH Zürich), V. Petrov (Univ. Michigan), A. Manera (ETH Zürich), Y. Rivera (Univ. Politècnica de València)

Employment of Proper Orthogonal Decomposition in Analysis of Experimental Measurements in a Hemispherical Upper Plenum

Blake R. Maher (TAMU), Noah Sutton (TAMU), Yassin A. Hassan (TAMU)

Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants

Ye Yeong Park (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)

Experimental Investigation of Heat Pipe Flow Dynamics and Performance

Ilyas Yilgor (Rensselaer Polytechnic Institute), Shanbin Shi (Rensselaer Polytechnic Institute)

Experimental Study on the Start-up of the Annular Wick Type Heat Pipe Using Fiber Optical Temperature Measurement Technique

Joseph Seo (TAMU), Hansol Kim (TAMU), Yassin A. Hassan (TAMU)

Experimental Study on the Characteristics of Thermal Interaction Between Liquid Metal with Water

Lin Zhang (Shanghai Jiao Tong Univ.), Chang Deng (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.)

Characterization of Thermal Time of Flight (TToF) Measurement Technique for Velocity Measurement of Gas Flow Using K-type Thermocouples and Fiber Bragg Grating Temperature Sensor

Zayed Ahmed (City College of New York), Giorgio Bologna (City College of New York), ElMokhtar Majdoub (City College of New York), Mathieu Davis (City College of New York), Abdullah Abubakar (City College of New York), Dinesh V. Kalaga (City College of New York), Masahiro Kawaji (City College of New York), Zhao Kchao (Univ. Pittsburgh), Yuqi Li (Univ. Pittsburgh), Kevin Chen (Univ. Pittsburgh)

Fiber Optic Flow Meter for High-Temperature Corrosive Nuclear Environments

M. Leoschke (Penn State), C. Balbier (Penn State), S. Lee (Penn State), F. Scurti (Penn State)

Pressure Field Reconstruction with PIV Experimental Velocity Field Inside Falling Liquid Film

Ruiqi Wang (Science and Technology on Thermal Energy and Power Lab), Riqiang Duan (Tsinghua Univ.), Zhenhai Zou (Science and Technology on Thermal Energy and Power Lab), Chonghai Huang (Science and Technology on Thermal Energy and Power Lab), Chenyang Wang (Science and Technology on Thermal Energy and Power Lab), Bangming Li (Science and Technology on Thermal Energy and Power Lab)

Design and Development of a Spacer Grids with Minimum Thermal-Hydraulic Impacts for Rod Bundle CHF Testing with Bowed or Ballooned Rods

Bao-Wen Yang (Delta Energy Group New York), Cameron Dempsey (Delta Energy Group New York), Bin Han (Delta Energy Group New York), Eric Yang (CARP Assoc. USA), Raymond Smith (CARP Assoc. USA), Stephanie H. Yang (CARP Assoc. USA)

Design of a High-Temperature Shaft Seal Test Facility for Molten Salt Pumps

Shuai Che (Univ. Michigan), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Yuqi Liu (Univ. New Mexico), Minghui Chen (Univ. New Mexico)

Experimental PIV Measurements in a Randomly Packed Non-Isothermal Pebble Bed Core Prototype

Abdulaziz Almathami (TAMU), Blake R. Maher (TAMU), Yassin A. Hassan (TAMU)

Helical Coil Steam Generator Experiments with the MOTEL SMR Test Facility in the EU-McSAFER Project

J. Telkkä (LUT Univ.), H. Suikkanen (LUT Univ.), A. Räsänen (LUT Univ.), E. Kotro (LUT Univ.), J. Hyvärinen (LUT Univ.)

Integral Effect Test on Operational Performance of PAFS (Passive Auxiliary Feedwater System) for Long Term Cooling Under an SBO (Station Black Out) Condition

Kyoung-Ho Kang (KAERI), Yusun Park (KAERI), Byoung-Uhn Bae (KAERI), Seok Kim (KAERI)

Experimental Study of Thick Rod Rewetting by a Falling Film

O. Kabesa (Ben Gurion Univ.), M. Harel (Ben Gurion Univ.), Y. Aharon (Nuclear Research Center Negev)

Advances in Integral and Separate Effects Experiments for Water-Cooled Small Modular Reactors

Palash K. Bhowmik (INL), Sabharwall Piyush (INL), Justin T. Johnson (INL), James E. O'Brien (INL), Clay Lietwiler (Holtec Int'l)

Efficiency of Passive Open Loop Heat Removal over Wide Range of Loop Flow Resistances -- PASI Loop Tests in the EU-PASTELS Project

J. Telkkä (LUT Univ.), V. Riikonen (LUT Univ.), A. Räsänen (LUT Univ.), E. Kotro (LUT Univ.), J. Hyvärinen (LUT Univ.)

Experiments of Helically Rifled Tubing Thermal Performance Using Additively Manufactured Test Sections for Molten Salt Applications

Ryan P. McGuire (Virginia Commonwealth Univ.), Landon Moore (Virginia Commonwealth Univ.), Arturo Cabral (Virginia Commonwealth Univ.), Connor F. Donlan (Virginia Commonwealth Univ.), James Vulcanoff (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.)

RPV Top and Bottom Break SBLOCA with Passive Emergency Core Cooling System Using ATLAS Test Facility

Seok Cho (KAERI), Byoung-Uhn Bae (KAERI), Yu-Sun Park (KAERI), Jae-Bong Lee (KAERI), Jong-Rok Kim (KAERI), Kyong-Ho Kang (KAERI)

A Preliminary Study on Performance Evaluation of 100 kW Printed Circuit Steam Generator for Small Modular Reactor Application

Hwang Bae (KAERI), Hyun-Gi Yoon (KAERI), Sunil Lee (KAERI), Jin-Hwa Yang (KAERI), Yoon Gon Bang (KAERI), Chanjong Seo (KAERI), Sung-Jae Yi (KAERI), Hyun-Sik Park (KAERI), Sang Ji Kim (KAERI), Sung Won Lim (KAERI)

Experimental Investigation on the Steam-Air Mixture Stratification in PCCS Using Condensation Heat Exchanger of Natural Circulation Loop

Jin-Hwa Yang (KAERI), Tae-Hwan Ahn (KAERI), Hong-Hyun Son (KAERI), Jin Su Kwon (KAERI), Hwang Bae (KAERI), Hyun-Sik Park (KAERI)

Development of a High-Prandtl Number Heat Transfer Correlation in the Near-Wall Region of a Pebble Bed

Sade Campos (Kairos Power), Griffen Latimer (Kairos Power), Seth Cadell (Kairos Power)

Development of an Integral Effects Test Facility for the Kairos Power Fluoride High-Temperature Reactor

Griffen Latimer (Kairos Power), Floren Rubio (Kairos Power), Seth Cadell (Kairos Power), Craig Gerardi (Kairos Power), David Sprinkle (Kairos Power), Eric Johnson (Kairos Power), Keith Johnson (Kairos Power)

Experimental Investigation of the Effect of RCIC Steam Exhaust Line Design on Suppression Pool Thermal Stratification

Kenneth Fossum (TAMU), Dallin Keesling (TAMU), Johnathan Smalley (TAMU), Karen Vierow Kirkland (TAMU)

Reflood Thermal-Hydraulics Testing Using the NRC-PSU Rod Bundle Heat Transfer (RBHT) Test Facility

Brian R. Lowery (Penn State), Molly K. Hanson (Penn State), Grant R. Garrett (Penn State), Douglas J. Miller (Penn State), Turki Almudhhi (Penn State), Fan-Bill Cheung (Penn State), Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Kirk Tien (U.S. Nuclear Regulatory Commission), Chris L. Hoxie (U.S. Nuclear Regulatory Commission)

Towards a Better Understanding of Reflood Thermal-Hydraulics: A Summary of the OECD/NEA RBHT Project

Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Brian Lowery (Penn State), Fan-Bill Cheung (Penn State), Alessandro Del Ferraro (NINE), Marco Cherubini (NINE), Alessandro Petruzzi (NINE), Jinzhao Zhang (Tractebel Engineering), Martina Adorni (OECD/NEA)

METERO-V and PRIUS Experimental Programs: Complementary Separate Effects Tests for Core Mixing Validation

Philippe Fillion (CEA), Seok Kim (KAERI), Clément Melin (CEA), Gilles Bernard-Michel (CEA), Benjamin Cariteau (CEA), Kyoung-Ho Kang (KAERI)

Primary Coolant Apparatus Test (PCAT): An Experimental Facility for MARVEL Microreactor

C. Parisi (INL), S. Yoon (INL), C. Baily (INL), B. Grover (INL), Y. Arafat (INL), S.J. Kim (LANL)

Scaling Analysis of a Separate Effects Test Facility for Thermal Performance Investigations of Heat Transfer Enhancements for Molten Salt Applications

Connor F. Donlan (Virginia Commonwealth Univ.), Arturo Cabral (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.)

Multi-Physics Safety Assessment of Core Thermal-Hydraulics Under Loss-of-Coolant Accident and Reactivity Initiated Accident

Sang-Ki Moon (KAERI), Jongrok Kim (KAERI), Yong-Seok Choi (KAERI), Jae Bong Lee (KAERI), Kihwan Kim (KAERI), Byong Guk Jeon (KAERI), Seok Kim (KAERI), Hyun-Sik Park (KAERI)

Coal Experiments Investigating the Reflooding of a 7 X 7 Rods Bundle During a Loss of Coolant Accident -- Effect of a Partially Blocked Area with Ballooned Rods

G. Repetto (IRSN), Q. Grando (IRSN), B. Bruyère (IRSN), S. Eymery (IRSN), R. Fortman (STERN Laboratories), R. Van Lochem (STERN Laboratories)

Experimental Investigation of Minimum Film Boiling Temperature During Reflood Transients

Turki K. Almudhhi (Penn State), Douglas J. Miller (Penn State), Grant R. Garrett (Penn State), Ian R. Lowery (Penn State), Fan-Bill Cheung (Penn State), Brian R. Lowery (Penn State), Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Kirk Tien (U.S. Nuclear Regulatory Commission), Chris L. Hoxie (U.S. Nuclear Regulatory Commission)

Spray Cooling of a Rod Bundle with a Counter-Current Steam Flow in Spent Fuel Pool Conditions

G. Brillant (IRSN)

Uniform and Non-Uniform Flows Through a PWR-Type Rod Bundle with Mixing Grids at Reynolds Number Ranging from 800 up to 70000: Pressure Loss Measurements

Clément Melin (CEA), Gilles Bernard-Michel (CEA), Benjamin Cariteau (CEA), Philippe Fillion (CEA)

Out-of-Pile Transient Blowdown Experiment

M. Moussaoui (Oregon State), T. Howard (Oregon State), G. Mignot (Oregon State), A. Weiss (Oregon State), W. Marcum (Oregon State)

Characteristics of Flow Boiling CHF on a Heater Rod Under Heaving Motion Conditions

Jin-Seong Yoo (Seoul Nat'l Univ.), Chang Won Lee (Seoul Nat'l Univ.), Heepyo Hong (Seoul Nat'l Univ.), Hyukjae Ko (Seoul Nat'l Univ.), Ja Hyun Ku (Seoul Nat'l Univ.), Goon-Cherl Park (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)

Wall Convective Heat Transfer Characteristics in the Inverted Annular Film Boiling Regime

Kyung Mo Kim (Univ. Michigan), Adam Burak (Univ. Michigan), Joseph Kelly (U.S. Nuclear Regulatory Commission), Stephen Bajorek (U.S. Nuclear Regulatory Commission), Xiaodong Sun (Univ. Michigan)

Transient Critical Heat Flux Experiments in Subcooled Flow

A. Camargo (Oregon State), G. Mignot (Oregon State), T. K. Howard (Oregon State), W. Marcum (Oregon State), A. Weiss (Oregon State)

Experimental Investigations of Rod Bundle Creep in Fluid-Structure Interaction

G.A.M. Vidal (CEA), E. Lo Pinto (CEA), V. Faucher (CEA), G. Ricciardi (French Alternative Energies and Atomic), N. Lamorte (Framatome), J. Pacull (Framatome)

Particle Image Velocimetry Measurements for Transition Flow Regime Through a Porous Blocked Subchannel in a 61-Pin Wire-Wrapped Bundle

Trevor Melsheimer (TAMU), Craig Menezes (TAMU), Matthew Kinsky (TAMU), Dalton Pyle (TAMU), Yassin A. Hassan (TAMU)

Experiment and Analysis on the Multi-Dimensional Flow Behavior Between Sub-Channels in the Rod-Bundle Array

Seok Kim (KAERI), Jee Min Yoo (KAERI), Byong Guk Jeon (KAERI), Sank-Ki Moon (KAERI)

Study on the Mixing Vane Grid Effect on Flow Field and Bubble Distribution in a 2x1 Subchannel by PIV and High Speed Camera

Bin Han (Xi’an Jiaotong Univ.), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy), Xiaoliang Zhu (Southeast Univ.), Aiguo Liu (Delta Energy Group)

Experimental Investigations of Material-Conjugated Subcooled Flow Boiling

Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)

The Effect of Time Varying Axial Power Shape on Transient Critical Power Performance of BWR Fuel

B. Ward (Global Nuclear Fuel Americas), S. Oh (Global Nuclear Fuel Americas), J. Andersen (Global Nuclear Fuel Americas), C. Heck (Global Nuclear Fuel Americas), D. Rock (Global Nuclear Fuel Americas), M. Sugawara (Global Nuclear Fuel Americas), J. Lamy (Global Nuclear Fuel Americas)

Steady-State and Power Transient Critical Heat Flux Experiments of FeCrAl and Zircaloy Claddings Under Saturated Pool Boiling

Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)

Experimental Research About Corrosion Effect on Boiling Heat Transfer Performance of Plate-Type Samples with Micro-Structures

Wei Xu (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Kun Ouyang (Shanghai Jiao Tong Univ.), Xiaoqiang He (Nuclear Power Institute of China)

PIV Investigation of Jet Mixing Induced by Direct Contact Condensation

M. Pellegrini (Univ. Tokyo), K. Okamoto (Univ. Tokyo), B. Blaisot (Univ. Tokyo), N. Erkan (Univ. Tokyo)

Flow Rate Measurement Across the Upper Core Structure of a Sodium Fast Reactor

D. Guenadou (CEA), P. Aubert (CEA), J-P Descamps (CEA)

High-Resolution Experiments for Mixing in Large Enclosures

J. Mao (Univ. Michigan), V. Petrov (Univ. Michigan), A. Manera (ETH Zürich)

Experimental Study of Stagnant Taylor Bubble in Counter-Current Flow

Iztok Tiselj (Jožef Stefan Institute), Jan Kren (Jožef Stefan Institute), Blaž Mikuž (Jožef Stefan Institute)

Initial Characterization of Observed Dispersion and Relocation Phenomena During a Loss of Coolant Accident (LOCA)

Sade Danielle Campos (Oregon State), Trevor Kent Howard (Oregon State), Grant Hendrickson (Oregon State), Aaron Weiss (Oregon State), Guillaume Mignot (Oregon State), Wade Marcum (Oregon State)

Comparison Between High-Resolution Gamma-ray Tomography and Wire-Mesh Sensor for Air-Water Flow in a Rod Bundle Geometry

Taehwan Ahn (Univ. Michigan), Victor Petrov (Univ. Michigan), Annalisa Manera (Univ. Michigan)

Flow Visualization of a Prototypical Helical Coil Bundle Section Undergoing Flow Induced Vibration

Noah Sutton (TAMU), Blake R. Maher (TAMU), Rodolfo Vaghetto (TAMU), Yassin Hassan (TAMU)

Experimental Investigation on Distribution of Boric Acid in a Vertical 1x2 Rod Array Channel

Long Ji (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Hui He (Shanghai Jiao Tong Univ.)

The STEAM Facility: Design and Analysis

A. Vannoni (Sapienza Univ. Rome), C. Ciurluini (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), P. Lorusso (ENEA), M. Eboli (ENEA), R. Marinari (ENEA), A. Tincani (ENEA), A. Del Nevo (ENEA)

Heat Transfer Characteristic of Natural and Forced Circulations in a Vertical Annulus in a Low Flow Condition

Youngchang Ko (Pusan National Univ.), Sanggyun Nam (Pusan National Univ.), Byongjo Yun (Pusan National Univ.)

Data-Driven Modeling of the Flow Field Between Two PWR Surrogate Bundles Under Seismic Conditions Using Bagging-Optimized Dynamic Mode Decomposition (BOP-DMD)

Haidy Ibrahim (Politecnico di Milano), Carolina Introini (Politecnico di Milano), Antonio Cammi (Politecnico di Milano), Roberto Capanna (George Washington Univ.), Philippe Bardet (George Washington Univ.), Guillaume Ricciardi (CEA)

Thermal and Hydraulic Performance Tests on the Factory Premises on a 18 MW Tubular Heat Exchanger to be Installed in a French Nuclear Power Plant

N. Lancial (EDF), J. Halleguen (EDVANCE), G. Wellenreiter (APAVE)

Aerosol Generation by Continuous Fiber Laser Irradiation of Various Surfaces and Spray Scavenging

Avadhesh Kumar Sharma (Univ. Tokyo), Ruicong Xu (Univ. Tokyo), Zeeshan Ahmed (Univ. Tokyo), Erdal Ozdemir (Univ. Tokyo), Shuichiro Miwa (Univ. Tokyo)

Experimental Investigation of the Post-Dryout Heat Transfer with R-134a at High Pressures

N. Rensch (Karlsruhe Institute for Technology), L. Köckert (Karlsruhe Institute for Technology), D. Klingel (Karlsruhe Institute for Technology), A. F. Badea (Karlsruhe Institute for Technology), X. Cheng (Karlsruhe Institute for Technology)

Experimental Study of Boiling Crisis on Helical Finned Heater Under Rolling Condition

Chang Won Lee (Seoul Nat'l Univ.), Jin-Seong Yoo (Seoul Nat'l Univ.), Heepyo Hong (Seoul Nat'l Univ.), Hyukjae Ko (Seoul Nat'l Univ.), Ja Hyun Ku (Seoul Nat'l Univ.), Goon-Cherl Park (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)

Experimental and Numerical Investigation on the Post-Dryout Behaviour of Debris Beds with Annular Downcomer

Markus Petroff (Univ. Stuttgart), Rudi Kulenovic (Univ. Stuttgart), Michael Buck (Univ. Stuttgart), Jörg Starflinger (Univ. Stuttgart)

Assessment of the Rewetting Phenomenon After DNB Events Under Prototypical PWR Conditions

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

Critical Power Sensitivity to Axial Power Shapes and Prediction by COBRAG Subchannel Code

S. Oh (Global Nuclear Fuel), B. Ward (Global Nuclear Fuel), J. Andersen (Global Nuclear Fuel), C. Heck (Global Nuclear Fuel), D. Rock (Global Nuclear Fuel), M. Sugawara (Global Nuclear Fuel), J. Lamy (Global Nuclear Fuel)

A New Paradigm for the Role of Disturbance Waves on Film Dryout in Annular Two-Phase Flow

Roman W. Morse (Univ. Wisconsin, Madison), Jason Chan (Univ. Wisconsin, Madison), Kristofer M. Dressler (Univ. Wisconsin, Madison), Gregory F. Nellis (Univ. Wisconsin, Madison), Arganthael Berson (Univ. Wisconsin, Madison), Jean-Marie Le Corre (Westinghouse Electric Sweden)

Liquid Level Monitoring and Quenching Front Tracking for SMR Rod Bundle CHF Tests Under Low Pressure, Low Flow, High Quality Conditions

Bao-Wen Yang (DEGNY Delta Energy Group New York), Cameron Dempsey (DEGNY Delta Energy Group New York), 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), Eric Yang (CARP Assoc. USA), Raymod Smith (CARP Assoc. USA)

Thermal Hydraulic Experiments and Code Validation for LWR SMRs Within the European McSAFER Project: Overview of Activities and Current Status

H. Suikkanen (LUT Univ.), J. Telkkä (LUT Univ.), V. Kouhia (LUT Univ.), S. Gabriel (Karlsruhe Institute for Technology), G. Albrecht (Karlsruhe Institute for Technology), W. Heiler (Karlsruhe Institute for Technology), F. Heineken (Karlsruhe Institute for Technology), V. H. Sanchez-Espinoza (Karlsruhe Institute for Technology), H. Li (Royal Institute of Technology), D. Grishchenko (Royal Institute of Technology), M. Bencik (Nuclear Research Institute Rez), L. Vyskocil (Nuclear Research Institute Rez), V. Dolecek (Nuclear Research Institute Rez), C. Queral (Univ. Politécnica de Madrid), K. Fernandez-Cosials (Univ. Politécnica de Madrid), L. Rueda Villegas (Tractebel ENGIE), C. R. Schneidesch (Tractebel ENGIE)

Measurement of Aerosol Mass Transfer and Hydrodynamics in a Bubble Column Using Wire-Mesh Sensors

Alvaro Ramos Perez (Paul Scherrer Institute), Terttaliisa Lind (Paul Scherrer Institute), Annalisa Manera (Paul Scherrer Institute), Victor Petrov (Paul Scherrer Institute), Horst-Michael Prasser (ETH Zürich)

RIVA: A New Experimental Facility for Fast Blowdown and Pressurization of Small Containment

Lucia Sargentini (CEA), Constantin Ledier (CEA), Arnaud Chazottes (CEA)

High-Fidelity Experiments of Turbulent Buoyant Jets from Simultaneous Particle Image Velocimetry and Laser Induced Fluorescence

Valentina Valori (ETH Zurich), Sunming Qin (INL), Victor Petrov (ETH Zürich), Annalisa Manera (ETH Zürich)

A Comprehensive Measurement of Bubbly Flow in a 30 mm x 10 mm Rectangular Channel

Dewei Wang (Virginia Tech), Yucheng Fu (Virginia Tech), Hanxing Sun (Virginia Tech), Yang Liu (Virginia Tech), Qingqing Liu (Univ. Michigan), Yang Liu (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Ted Worosz (Naval Nuclear Laboratory), John Buchanan (Naval Nuclear Laboratory)

A 3-D Imaging System for Bubbly Flow Measurement

Yucheng Fu (Virginia Tech), Dewei Wang (Virginia Tech), Yang Liu (Virginia Tech), Xiaodong Sun (Univ. Michigan), Ted Worosz (Naval Nuclear Laboratory), John Buchanan (Naval Nuclear Laboratory)

Experimental Study of Air-Water Two-Phase Flow Threshold Velocities in a Vertical Annular Channel

A. Biton (Nuclear Research Center Negev), E. Rabinovich (Nuclear Research Center Negev), E. Gilad (Ben Gurion Univ. Negev)

Experimental Study and CFD Simulation of Air-Water Bubbly Flow in a Rectangular Channel

Qingqing Liu (Univ. Michigan), Yang Liu (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Dewei Wang (Virginia Tech), Yang Liu (Virginia Tech), John R. Buchanan (Naval Nuclear Laboratory), Ted Worosz (Naval Nuclear Laboratory)

One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations

Drew Ryan (Purdue), Seungjin Kim (Purdue)

Two Scale Two-Flux Model for Density Wave and Slug Flow Instabilities

Alejandro Clausse (Purdue), Alexander Lopez-de-Bertodano (Univ. Chicago), Martin Lopez-de-Bertodano (Purdue)

Gas Ingress During Side Vessel Break: Experiments and Numerical Simulations with a Simplified Pool-Type Scaled Water Model

M. Faruoli (von Karman Institute for Fluid Dynamics), M. Delsipee (von Karman Institute for Fluid Dynamics), Ph. Planquart (von Karman Institute for Fluid Dynamics), G. Scheveneels (SCK CEN), B. Yamaji (SCK CEN)

Vapor Pressure and Temperature Analyses on a Gravity-Assisted Wrapped Screen Wick Annular Heat Pipe

Daniel Orea (TAMU), N.K. Anand (TAMU), Yassin A. Hassan (TAMU)

Experimental Investigation of Two-Phase Pressure Drop and Flow Regime Visualization in Chevron-Type Plate Heat Exchangers

Stefano Passoni (Politecnico di Milano), Riccardo Mereu (Politecnico di Milano), Stefano Lorenzi (Politecnico di Milano), Fabio Inzoli (Politecnico di Milano), Marco Enrico Ricotti (Politecnico Di Milano)

Study on the Effect of Length to Diameter Ratio on Critical Flow Based on RELAP5/MOD3.3 Simulations

Wenda Liu (North China Univ. Electric Power), Xinguo Yu (North China Univ. Electric Power)

Influence of Reactor Cavity Cooling System Design Parameters on Heat Transfer for a Prototypical gFHR

Khaled Talaat (Univ. New Mexico), Minghui Chen (Univ. New Mexico)

Analytical Investigation on Fluid Flow and Heat Transfer Characteristics in a Natural Circulation Loop for an Integral Type Reactor

Hyun-Sik Park (KAERI), Hwang Bae (KAERI), Sung-Uk Ryu (KAERI), Sunil Lee (KAERI), Jin-Hwa Yang (KAERI), Byong-Guk Jeon (KAERI), Sung-Jae Yi (KAERI)

1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops

G. Benzoni (Politecnico di Milano), C. Introini (Politecnico di Milano), A. Cammi (Politecnico di Milano), S. Lorenzi (Politecnico di Milano)

Natural Circulation Test and Non-Condensable Gas Effect on a Two-Phase Thermosyphon Loop

Dahoon Jeong (Gyeongsang Nat'l Univ.), Seyeon Hwang (Gyeongsang Nat'l Univ.), Hyewon Kim (Gyeongsang Nat'l Univ.), Hyungmo Kim (Gyeongsang Nat'l Univ.), Dong Eok Kim (Chung-Ang Univ.)

Vaporization at High Reduced Pressure Induced by Very Rapid Power Input

J. Muller (IRSN), P. Ruyer (IRSN), R. Rullière (Univ. Lyon), M. Clausse (Univ. Lyon)

A Study on Boiling Entrainment from a Liquid Film on a Heated Surface

Raka Firman B. P. (Univ. Electro-Communications), Tomio Okawa (Univ. Electro-Communications), Yuki Narushima (Hitachi, Ltd.), Hajime Furuichi (Hitachi), Kenichi Katono (Hitachi)

Critical Heat Flux Dependence on Liquid Height in Subcooled Pool Boiling

Rodrigo Cavalcanti Alvarez (MIT), Matteo Bucci (MIT)

Predictions of Westinghouse TRITON11 BWR Fuel Critical Power Performances with MEFISTO-T Subchannel Analysis Code

Jean-Marie Le Corre (Westinghouse Electric Sweden)

Experimental Characterization of Heat Transfer Mechanisms in the Flow Boiling of Water on Surfaces with Engineered Micropillars

Chi Wang (MIT), Md Mahamudur Rahman (Univ. Texas, El Paso), Matteo Bucci (MIT)

A New Approach to CHF Modeling Based on ML Technology for PWR Design Applications

Yixing Sung (Westinghouse Electric Co.), Emre Tatli (Westinghouse Electric Co.), Alexander Mace (Westinghouse Electric Co.), Sukhwans Singh (Westinghouse Electric Co.), Michael Bettencourt (Westinghouse Electric Co.), Mario Buczkowski (Westinghouse Electric Co.), Raji Kosloske (Westinghouse Electric Co.), Gregory R. Williams (Westinghouse Electric Co.)

Investigation of the Stochastic Nucleation Timing and Site Distribution on Boiling Heat Transfer with Bubble Tracking Method

Heepyo Hong (Seoul Nat'l Univ.), Ja Hyun Ku (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)

Enhancing Nanoscale Heat Pipe with Hydrophilic/hydrophobic Pattern: A Molecular Dynamics Study

Wei Deng (City Univ. Hong Kong), Jiyun Zhao (City Univ. Hong Kong)

A Study of Wall Heat Flux Partitioning Model for Subcooled Boiling Flow

Manh Long Doan (Pusan National Univ.), Jeongmin Moon (Pusan National Univ.), Youngchang Ko (Pusan National Univ.), Jae Jun Jeong (Pusan National Univ.), Byongjo Yun (Pusan National Univ.)

AC2-ATHLET Simulations of PERSEO Test Facility

Sebastian Buchholz (GRS)

Temperature Dependence on Advancing and Receding Contact Angles of Water on Smooth Stainless Steel Surface Under Elevated Pressure: Preliminary Results of an Experimental Study

Guo-Tao Fu (Zhejiang Univ.), Li-Wu Fan (Zhejiang Univ.), Jia-Wen Song (Univ. Calgary)

The Effect of Data Split on Correlation Errors with Respect to Independent Validation Data

Kanghoon Kim (KEPCO Nuclear Fuel), Boemjun Jang (KEPCO Nuclear Fuel)

Investigation of the DNBR Criteria Application for NPP Safety Studies

Attila Guba (Centre for Energy Research), Áron Hegedüs (Centre for Energy Research)

SMR Rod Bundle CHF-Characteristics and Challenges in Experimental Investigation

Bao-Wen Yang (Delta Energy Group), Aiguo Liu (Delta Energy Group), Bin Han (Delta Energy Group)

DNB Prediction for a Subcooled Flow Boiling in a Rolling Pipe Using CFD

Nam kyu Ryu (Chungnam Nat'l Univ.), Byoung jae Kim (Chungnam Nat'l Univ.)

Low Pressure Low Flow Rod Bundle CHF and its Challenges in SMR

Bao-Wen Yang (DEQD), Bin Han (Southeast Univ.), Aiguo Liu (DEQD)

Scaled Validation Test for High Prandtl Number Fluid Mixed Convection Between Parallel Plates with Symmetric and Asymmetric Boundary Conditions

Floren Rubio (Kairos Power), Johnathan Gilbreth (Kairos Power), Seth Cadell (Kairos Power), Alexander Heald (Kairos Power), Haihua Zhao (Kairos Power), Brandon P. Haugh (Kairos Power)

Scaling Effects in Intermediate Break LOCA Scenarios

Kevin Martin (UPC), Jordi Freixa (UPC), Victor Martinez-Quiroga (UPC)

Digitilization, Management and Synthesis of Thermal Hydraulic Legacy Data Using Dynamical System Scaling

Stephen A. Heagy (FPoliSolutions), Cesare Frepoli (FPoliSolutions), José N. Reyes (NuScale Power)

The use of System Codes for Scaling Analysis and the use of Scaling Tools for the Analysis of Code Predictions

D. Bestion (Consultant), A. Ciechocki (CEA), S. Carnevali (CEA)

Comparison of Dynamical System Scaling and Hierarchical Two-Tiered Scaling Applications with Definite Solution Analogy Theory to the Passive Residual Heat Removal System of Fluoride-Salt-Cooled High-Temperature Advanced Reactor

Xinyu Li (Xi’an Jiaotong Univ.), Dalin Zhang (Xi’an Jiaotong Univ.), Xingguang Zhou (Xi’an Jiaotong Univ.), Xindi Lv (Xi'an Jiaotong University,), Dianqiang Jiang (Xi’an Jiaotong Univ.), Zhiyuan Wu (Xi’an Jiaotong Univ.), Sijun Li (Xi’an Jiaotong Univ.), Wenxi Tian (Xi'an Jiao Tong University), Suizheng Qiu (Xi’an Jiaotong Univ.), G.H. Su (Xi’an Jiaotong Univ.)

Natural Convection Heat Transfer with Molten Salt in a Differentially-Heated Cavity

Noah LeFrancois (McGill Univ.), Jovan Nedic (McGill Univ.), Melanie Tetreault-Friend (Hatch)

A Study of Laminar-Turbulent Transition in Rod Bundles

L. C. Aldeia Machado (Penn State), C. Bourdot Dutra (Penn State), S. P. Bistany (Penn State), E. Merzari (Penn State)

Zero-Emission Mobile Carbon Capture Facility Powered By Decay Heat of Nuclear Spent Fuels

Muyue Li (Univ. Michigan), Zhenyu Fei (Univ. Michigan), Kunzhe Bao (Univ. Michigan), Boren Ke (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Lumin Wang (Univ. Michigan)

Mechanistic Modeling of Interfacial Area Transport for Vertical Round Pipes over Wide Range of Pipe Diameters

Zhuoran Dang (Univ. Calgary), Mamoru Ishii (Purdue), Yang Zhao (Purdue)

Pebble Flow and Residence Time Distribution of 6.0 cm Graphite Pebbles in a Recirculating Pebble Bed Experimental Setup Using Radioactive Particle Tracking Technique

Ahmed Jasim (Missouri Univ. Science and Technology), Jihane Mendil (Missouri Univ. Science and Technology), Omar Farid (Missouri Univ. Science and Technology), Zeyad Zeitoun (Missouri Univ. Science and Technology), Sebastian Uribe (Missouri Univ. Science and Technology), Muthanna H. Al-Dahhan (Missouri Univ. Science and Technology)

Automated Thermal Hydraulics System Analysis of High Flux Isotope Reactor Low-Enriched Uranium Silicide Dispersion Fuel Designs

Christopher J. Hurt (ORNL), Zachary A. Bacon (ORNL), Valerie D. Fudurich (ORNL), W. Christopher Lowe (ORNL)

3D Imaging of Phase Structures Using Fibre Bragg Grating Grid Sensors

Harvey Oliver Plows (Bangor Univ.), Marat Margulis (Bangor Univ.), Jinfeng Li (Bangor Univ.)

Modeling and Simulation-Informed Design of a Natural Convection Salt Loop Irradiation Experiment at MITR to Generate MSR-Specific Data

Nesrin O. Cetiner (MIT), David Carpenter (MIT), Guiqiu Zheng (MIT), Gordon Kohse (MIT)

COMSOL Multiphysics Modeling Results for the Low Enriched Uranium-Silicide Conversion of the High Flux Isotope Reactor

Prashant K. Jain (ORNL)

Flow Visualization in a Packed Bed Using Positron Emission Particle Tracking (PEPT) and X-Ray Computed Tomography (CT)

Adam O. Mafi (Virginia Commonwealth Univ.), Arturo Cabral (Virginia Commonwealth Univ.), Jerel W. Houston (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.), Cody S. Wiggins (ORNL)

Large Eddy Simulations of Channel Flow with one Heated Wall for Liquid Metals and High Temperature Gasses

Theodore M. Chu (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.)

Large Eddy Simulation of Thermal Mixing of Liquid Sodium in a T-Junction

Xiaoxue Huang (Univ. Sheffield), Shuisheng He (Univ. Sheffield)

Measurements of Near-Wall Turbulence in Water by Molecular Tagging Velocimetry

Charles Fort (George Washington Univ.), Philippe Bardet (George Washington Univ.)

Code Calculation of Flow Distributions in a Plate-Type Fuel Assembly

Zhou Lei (Nuclear Power Institute of China), Liu Jingze (Nuclear Power Institute of China), Yang Jun (Nuclear Power Institute of China)

Flow Reconstruction of Jet Induced by Steam Condensation from Sparse Temperature Measurements

Xicheng Wang (Royal Institute of Technology), YiMeng Chan (Royal Institute of Technology), Dmitry Grishchenko (Royal Institute of Technology), Pavel Kudinov (Royal Institute of Technology)

Integrating Physics into Machine Learning for Time Series Forecasting of Dynamic Thermal-Hydraulic Systems

Xingang Zhao (ORNL), Bryan Maldonado Puente (ORNL), Wesley Williams (ORNL), Seung-Hwan Lim (ORNL), Frank Liu (ORNL), Pradeep Ramuhalli (ORNL)

Embedded Borescopic Molecular Tagging Velocimetry Within PWR Surrogate Bundle

Roberto Capanna (George Washington Univ.), Philippe M. Bardet (George Washington Univ.), Guillaume Ricciardi (CEA)

Simultaneous High-Speed Flow Velocimetry and Pressure Measurements in Water Hammer

Roberto Capanna (George Washington Univ.), Philippe M. Bardet (George Washington Univ.)

Effects of Multiple Melt-Jets Release and Triggering on the Energetics of Ex-Vessel Steam Explosion in Nordic BWRs

Ibrahim Batayneh (Royal Institute of Technology), Dmitry Grishchenko (Royal Institute of Technology), Pavel Kudinov (Royal Institute of Technology)

Modeling of Triggering and Steam Explosion Pressure Propagation with Validation Against KROTOS Experiments

Ibrahim Batayneh (Royal Institute of Technology), Dmitry Grishchenko (Royal Institute of Technology), Pavel Kudinov (Royal Institute of Technology)

Lagrangian-Eulerian Coupled Numerical Modeling of Fuel-Coolant Interaction in Nuclear Reactor Severe Accident

M.S. Kim (Korea Maritime and Ocean Univ.), D.J. Shin (Korea Maritime and Ocean Univ.), D.H. Kim (Korea Maritime and Ocean Univ.), K.H. Bang (Korea Maritime and Ocean Univ.)

Parametric Study of Modeling of Pool Scrubbing Under Jet Injection Regime Using GOTHIC

Xicheng Wang (Royal Institute of Technology), Dmitry Grishchenko (Royal Institute of Technology), Pavel Kudinov (Royal Institute of Technology)

The Effect of Aerosol Particle Density on Aerosol Release Potential in LMR Source Term Experiments

John C. Petrykowski (Vibration Heat Flow and Analysis)

Post-Test Analysis of SIRIO Facility Data by System Thermal-Hydraulic Codes for LFR Application

T. Del Moro (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), G. Khalil Youssef (Sapienza Univ. Rome), P. Lorusso (ENEA), M. Caramello (Ansaldo Nucleare), M. Cauzzi (SIET), M. Tarantino (ENEA)

Experimental Research of the MYRRHA Primary Pump Hydraulic Characteristics at a Reduced Scale

Mikhail Iarmonov (SCK CEN), Katrien V. Tichelen (SCK CEN)

Asymmetric Decay Heat Removal in MYRRHA: Experiments in the E-SCAPE Facility

J. Pacio (SCK CEN), R. Serrano Diogo (SCK CEN), K. Van Tichelen (SCK CEN)

Thermal-Hydraulic Analysis of the FFTF LOFWOS Transient with the SPECTRA Code

F. Alcaro (Nuclear Research & Consultancy Group), M.M. Stempniewicz (Nuclear Research & Consultancy Group)

Multiscale Effects in Sodium Fast Reactors: Feedback from the Open Phase of the FFTF LOFWOS-13 Test

Antoine Gerschenfeld (CEA), Yannick Gorsse (CEA), Simon Li (CEA)

NekRS CFD Simulations of Interassembly Flow in Sodium Fast Reactors

A.J. Novak (ANL), C. Bourdot Dutra (Penn State), D. Shaver (ANL), E. Merzari (Penn State)

Flow Decomposition and Reconstruction Using Proper Orthogonal Decomposition for a Porous Blocked Subchannel in a 61-Pin Wire-Wrapped Fuel Assembly

Craig Menezes (TAMU), Matthew Kinsky (TAMU), Trevor Melsheimer (TAMU), Dalton Pyle (TAMU), Yassin A. Hassan (TAMU)

RANS Simulations of Jet Flow and Thermal Stratification Phenomena in the TALL-3D Facility Subjected to Different Flow Regimes

M.M.M.D. Hussain (Nuclear Research & Consultancy Group), H.J. Uitslag-Doolaard (Nuclear Research & Consultancy Group), F. Roelofs (Nuclear Research & Consultancy Group), X. Huang (Univ. Sheffield), S. He (Univ. Sheffield)

Numerical Simulation of Turbulent Mixing in Wire-Wrapped Fuel Assembly of Liquid Lead-Bismuth-Cooled Fast Reactor

Sipeng Wang (Nanjing Univ. Aeronautics and Astronautics), Qindong Zhang (Nanjing Univ. Aeronautics and Astronautics), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer)

Modeling the Prismatic HTGR Core in SAM by Representative Channels

Taiyang Zhang (Univ. Illinois, Urbana-Champaign), Thanh Hua (ANL), Zhiee Jhia Ooi (ANL), Ling Zou (ANL), Caleb S. Brooks (Univ. Illinois, Urbana-Champaign)

A Demonstration of the Risk-Informed NEI 18-04 Design Evaluation Model for the Modular High Temperature Gas Reactor

Cesare Frepoli (FPoliSolutions), Stephen A. Heagy (FPoliSolutions), Jarrett Valeri (FPoliSolutions), Robert P. Martin (BWXT Advanced Technologies), Curtis L. Smith (INL), Kurt G. Vedros (INL)

Analysis of Flow Area in the Axial Cross-Vessel Annular Duct Following a Breach of the Primary Helium Boundary of an HTGR

Silvino A. Balderrama Prieto (INL), David J. Arcilesi (Univ. Idaho)

Optimization of the Emergency Coolant Injection System of ALLEGRO

Boris Kvizda (VUJE), Slavomír Bebjak (VUJE)

High-Fidelity Simulation of Pebble Beds: Toward an Improved Understanding of the Wall Channeling Effect

David Reger (Penn State), Elia Merzari (Penn State), Saya Lee (Penn State), Paolo Balestra (INL), Yassin A. Hassan (TAMU)

Design and Construction of an Integral-Effect Test Facility FLUSTFA for Molten Salt Reactor Applications

Sheng Zhang (Univ. Michigan), Hsun-Chia Lin (Univ. Michigan), Minghui Chen (Univ. Michigan), Shanbin Shi (Univ. Michigan), Shuai Che (Univ. Michigan), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Qiuping Lv (ANL)

Initial Operation of a High-Temperature Fluoride Salt Test Facility (FLUSTFA): Issues Identified and Paths Forward

Sheng Zhang (Univ. Michigan), Shuai Che (Univ. Michigan), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan)

Design of a Natural Circulation Experiment to Investigate Flow Stability

J.S. Narvaez Arrua (Univ. Grenoble Alpes), P. Rubiolo (Univ. Grenoble Alpes), J. Giraud (Univ. Grenoble Alpes), V. Ghetta (Univ. Grenoble Alpes), A. Cammi (Politecnico di Milano), S. Lorenzi (Politecnico di Milano)

Flow-Informed Corrosion in Molten Salts Using the Poisson-Nernst-Planck Model

M. Tano (INL), S. Walker (INL), A. Abou-Jaoude (INL)

Fuel Flow Modeling Under Thermal Fluidics Considerations Within Operational Domains of Molten Salt Reactors

Thabit M. Abuqudaira (TAMU), Pavel V. Tsvetkov (TAMU), Piyush Sabharwall (INL)

Investigation of Static Boiling in a Large Scale RCCS

Q. Lv (ANL), M. Jasica (ANL), D. Lisowski (ANL), Z. Ooi (ANL), A. Kraus (ANL), R. Hu (ANL), M. Farmer (ANL)

Uncoupled DEM Simulation to Investigate the Impact of Coolant Flow on Pebble Flow in Pebble Bed Reactor

Muhammad Sohaib Malik (Univ. Illinois, Urbana-Champaign), Jiaqi Chen (Univ. Illinois, Urbana-Champaign), Angela Di Fulvio (Univ. Illinois, Urbana-Champaign), Caleb S. Brooks (Univ. Illinois, Urbana-Champaign), Timothy P. Grunloh (Univ. Illinois, Urbana-Champaign)

The Refractive Index Matched Pebble Bed Facility for High Resolution Experiments of DLOFC and PLOFC Accidents in MPBRs

Zachary Welker (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan), Paolo Balestra (INL)

Turbulence Characteristics Using Dynamic Mode Decomposition in an 84-Pin Hexagonal Fuel Assembly

Craig Menezes (TAMU), Yassin A. Hassan (TAMU)

Development and First Application of a Simplified Tool for the Design of a Molten Salt Reactor

E. Martin Lopez (CEA), L. Matteo (CEA), V. Pascal (CEA), M. Mascaron (CEA), A. Petrilli (CEA)

Transient Modeling and Simulation of a Generic Stable Salt Reactor

Thanh Hua (ANL), Yan Cao (ANL), Rui Hu (ANL), Andrew Ballard (Moltex Energy Canada), David Catalan (Moltex Energy Canada)

Benchmarking MSRE Reactivity Insertion Tests Using SPECTRA and SAM

Marek Stempniewicz (Nuclear Research & Consultancy Group), Ferry Roelofs (Nuclear Research & Consultancy Group), Ting Fei (ANL), Thanh Hua (ANL), Bo Feng (ANL), Rui Hu (ANL)

Simulations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements for Molten Salts

James R. Vulcanoff (Virginia Commonwealth Univ.), Ryan P. McGuire (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.)

Implementation of a Gas Transport Model in SAM for Modeling Molten Salt Reactors

Robert Salko (ORNL), Travis Mui (ANL), Rui Hu (ANL), Ling Zou (ANL)

Investigation of Cladding Thermal Behavior Under Simulated Reflood Conditions

Cole Dunbar (Univ. Wisconsin, Madison), WooHyun Jung (Univ. Wisconsin, Madison), Thomas Demo (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison), Kumar Sridharan (Univ. Wisconsin, Madison), Hwasung Yeom (Univ. Wisconsin, Madison), Robert Armstrong (INL), David Kamerman (INL), Benjamin Maier (Westinghouse Electric Co.), Andrew Hoffman (General Electric Research), Raul Rebak (General Electric Research)

Chromium Oxidation Model Implementation in Best-Estimate Thermal-Hydraulic System Code for Accident Tolerant Fuel

Dong-Young Lee (FNC Technology Co.), Tae-sun Ro (FNC Technology Co.), Bub-Dong Chung (FNC Technology Co.), YoungJae Park (FNC Technology Co.), Soon-Joon Hong (FNC Technology Co.)

Application of Half-Boundary Method in Solving Annular Fuel Temperature Field

Boxue Wang (North China Electric Power Univ.), Mei Huang (North China Electric Power Univ.), Yaodi Li (North China Electric Power Univ.)

Study on Performance Evaluation of 2x2 Annular Fuel with Spacer Grid in PWR

Sipeng Wang (Nanjing Univ. Aeronautics and Astronautics), Zhuoyao Li (Nanjing Univ. Aeronautics and Astronautics), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer)

Research and Application of Annular Fuel Performance Analysis Models Applicable to Fast Reactor

Qihao Tao (Xi’an Jiaotong Univ.), Zhiyuan Xia (Xi’an Jiaotong Univ.), Bo Zhang (Xi’an Jiaotong Univ.)

Air Ingress and DLOFC Studies in Scaled HTGR Geometry Using Additively Manufactured TCR Fuel Elements

Broderick Sieh (Purdue), Hitesh Bindra (Purdue), Prashant Jain (ORNL), Christian Petrie (ORNL), Nathan See (ORNL)

Accident Analysis Modeling of General Atomics Fast Modular Reactor Plant Using MELCOR: DLOFC and PLOFC

WooHyun Jung (Univ. Wisconsin, Madison), Cole Dunbar (Univ. Wisconsin, Madison), Ryan Som (Univ. Wisconsin, Madison), Seung Kyo Jung (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison)

The Effects of Depressurizing into a Cavity for Small and Medium Sized Break Air Ingress Accident Scenarios

Zachary Welker (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan), Paolo Balestra (INL)

Investigation of Hybrid Heat Pipe Shutdown Rod Concept of Microreactor as a Passive Safety System

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

Thermal Stress Analysis for Heat Pipe Cooled Microreactor Core Varying Condenser Temperature

Myung Jin Jeong (Seoul Nat'l Univ.), San Lee (Seoul Nat'l Univ.), Jaeuk Im (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)

Experimental Study on the Start-up Characteristics and Performance of a Ten Sodium Heat Pipe Bundle Array

Pei-Hsun Huang (Univ. Michigan), Taehwan Ahn (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan)

Nuclear Spaceship for Interplanetary Cruise Using a Micro Fast Reactor　

Tadashi Narabayashi (Tokyo Institute of Technology)

Study on Startup Characteristic of a Supercritical Carbon Dioxide Brayton Cycle Coupled with Heat Pipe Cooled Reactor

Zheng Wang (Xi’an Jiaotong Univ.), Minghui Zhang (Xi’an Jiaotong Univ.), Shihao Xu (Xi’an Jiaotong Univ.), Junli Gou (Xi’an Jiaotong Univ.), Jianqiang Shan (Xi’an Jiaotong Univ.)

Development of Numerical Analysis Method of Oxygen Concentration near Wall of Lead-Bismuth Eutectic Channel

N. Kondo (Japan Atomic Energy Agency), S. Yamashita (Japan Atomic Energy Agency), S. Uesawa (Japan Atomic Energy Agency), K. Nishihara (Japan Atomic Energy Agency), H. Yoshida (Japan Atomic Energy Agency)

lbh15: A Python Package Implementing Lead, Bismuth, and Lead-Bismuth Eutectic Thermophysical Properties for Fast Reactor Applications

Daniele Panico (newcleo), Daniele Tomatis (newcleo)

IAEA's Coordinated Research Projects and Activities on Thermal Hydraulics of Fast Reactors

Nikoleta Morelova (IAEA), Vladimir Kriventsev (IAEA), Tyler Sumner (ANL), Anton Moisseytsev (ANL), Florent Heidet (ANL), David W. Wootan (PNNL), A. M. Casella (PNNL), J. V. Nelson (PNNL), Ivan Di Piazza (ENEA), H. Hassan (ENEA), Pierdomenico Lorusso (ENEA), Daniele Martelli (ENEA)

Research on Fuel Element Positioning Structure and Heat Transfer Characteristics of the Lead-Bismuth Cooled Fast Reactor

Linna Feng (Xi’an Jiaotong Univ.), Chao Guo (NPIC), ZhengYu Qian (Xi’an Jiaotong Univ.), Di Yun (Xi’an Jiaotong Univ.)

Convective Heat Transfer Characteristics Within a Shipping Container Transporting a Micro-HTGR

T-Ying Lin (Purdue), Hitesh Bindra (Purdue), Piyush Sabharwall (INL), Richard Schultz (Idaho State)

Development of Design Basis Safety Analysis Phenomena Identification and Ranking Table for the eVinci Microreactor

Michael J. Patterson (Westinghouse Electric Co.), Jun Liao (Westinghouse Electric Co.), Megan E. Durse (Westinghouse Electric Co.), William Brown (Westinghouse Electric Co.), Richard F. Wright (Westinghouse Electric Co.)

Benchmark Studies of the MOOSE-Based Sockeye and BISON Codes for the eVinci Heat Pipe Microreactor

Michael A. Shockling (Westinghouse Electric Co.), Megan E. Durse (Westinghouse Electric Co.), Liping Cao (Westinghouse Electric Co.), John Lojek III (Westinghouse Electric Co.), Rory A.F. Blunt (Westinghouse Electric Co.)

CFD Thermal Analysis of eVinci™ Microreactor -- Integrating Reactor Core and Primary Heat Exchanger

Hong Xu (Westinghouse Electric Co.), Liping Cao (Westinghouse Electric Co.)

Size Assessment of the Heat Exchanger for He-Xe Closed Brayton Cycle Applied in Mobile, Land-Based Microreactor System

Chaoran Guan (Shanghai Jiao Tong Univ.), Xiang Chai (Shanghai Jiao Tong Univ.), Tengfei Zhang (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.)

CFD - STH Code Coupling for the Thermal Hydraulic Analysis of NACIE-UP Experimental Facility

P. Cioli Puviani (Politecnico di Torino), R. Zanino (Politecnico di Torino), T. Del Moro (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), B. Gonfiotti (ENEA), I. Di Piazza (ENEA), D. Martelli (ENEA), M. Tarantino (ENEA)

Transient Behavior of Multi-Dimensional Core Cooling by D-DHX in Sodium-Cooled Fast Reactors

T. Ezure (Japan Atomic Energy Agency), Y. Akimoto (Japan Atomic Energy Agency), T. Onojima (Japan Atomic Energy Agency), A. Kurihara (Japan Atomic Energy Agency), M. Tanaka (Japan Atomic Energy Agency)

Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors

A. Lombardo (Politecnico di Torino), G.F. Nallo (Politecnico di Torino), N. Abrate (Politecnico di Torino), S. Dulla (Politecnico di Torino)

Multi-Physic Coupled Simulation of the Loss of Flow WithOut Scram Transient of the Fast Flux Test Facility

Simon Li (CEA), Héloïse Velardo (CEA), Georis Billo (CEA), Pierre Sciora (CEA), Matteo Monegaglia (CEA)

Passive Temperature-Sensitive Flow-Controlling Device Based on Bimetallic Membrane Deflection, FEM, and CFD Feasibility Study

Victor Petrov (Univ. Michigan), Yucan Ding (Univ. Michigan)

Thermal Hydraulic Design of a Heat Removal System for a Fusion Accelerator

R. Marinari (ENEA), M. Lamberti (ENEA), P. Agostini (ENEA), G. Gadani (ENEA), A. Mancini (ENEA), A. Pietropaolo (ENEA), Massimo Angiolini (ENEA), Ciro Alberghi (Politecnico di Torino), Luigi Candido (Politecnico di Torino), Marco Capogni (ENEA), Mauro Capone (ENEA), Sebastiano Cataldo (ENEA), Flavio Cicconi (ENEA), Gian Marco Contessa (ENEA), Francesco D'Annibale (ENEA), Marco D'Arienzo (ASL Roma 6), Alessio Del Dotto (ENEA), Dario Diamanti (ENEA), Danilo Dongiovanni (ENEA), Mirko Farini (ENEA), Paolo Ferrari (ENEA), Angela Fiore (ENEA), Davide Flammini (ENEA), Manuela Frisoni (ENEA), Gianni Gadani (ENEA), Angelo Gentili (ENEA), Giacomo Grasso (ENEA), Manuela Guardati (ENEA), David Guidoni (ENEA), Marco Lamberti (ENEA), Luigi Lepore (ENEA), Andrea Mariani (ENEA), Giuseppe A. Marzo (ENEA), Bruno Mastroianni (ENEA), Fabio Moro (ENEA), Vincenzo Narcisi (ENEA), Agostina Orefice (ENEA), Valerio Orsetti (ENEA), Tonio Pinna (ENEA), Antonietta Rizzo (ENEA), Alexander Rydzy (ENEA), Stefano Salvi (ENEA), Demis Santoli (ENEA), Alessia Santucci (ENEA), Luca Saraceno (ENEA), Camillo Sartorio (ENEA), Valerio Sermenghi (ENEA), Emanuele Serra (ENEA), Andrea Simonetti (ENEA), Nicholas Terranova (ENEA), Silvano Tosti (ENEA), Alberto Ubaldini (ENEA), Marco Utili (ENEA), Konstantina Voukelatou (ENEA), Danilo Zola (ENEA), Giuseppe Zummo (ENEA)

Heat Pipe Cooling System Reliability Analysis with Cascading Effect

Gyun Seob Song (Chung-Ang Univ.), Man Cheol Kim (Chung-Ang Univ.)

Heat Transfer Characteristics Analysis of Supercritical Water in 2x2 Wire-Wrapped Rod Bundles Based on Field Synergy Principle

Xuebin Zhao (Nuclear Power Institute of China), Hui Xiao (Nuclear Power Institute of China), Jinguang Zang (Nuclear Power Institute of China), Yanping Huang (Nuclear Power Institute of China)

Development and Modification of Pool Scrubbing Decontamination Factor Evaluation in Severe Accident Code

Weiyi Yao (Univ. Tokyo), Marco Pellegrini (Univ. Tokyo), Koji Okamoto (Univ. Tokyo)

Investigation of Starting Time Characteristics of Source Term Release for Dissimilar Nuclear Accident Consequence

Wasin Vechgama (KAERI), Jaehyun Cho (Chung-Ang Univ.)

Methyl Iodide Retention in Ag-Zeolite Material Under Filtered Containment Venting System Condition

F. Espegren (Paul Scherrer Institute), D. Suckow (Paul Scherrer Institute), T. Lind (Paul Scherrer Institute), J. Mantzaras (Paul Scherrer Institute), J. Theile (Paul Scherrer Institute)

Severe Accident Analysis of CANDU Plant Using CAISER Code

Jun-young Kang (KAERI), Dong Gun Son (KAERI), Yong Mann Song (KAERI), Jong Yeob Jung (KAERI), Jun Ho Bae (KAERI)

An Analysis of Effects and a Validation of Pressure Tube Ballooning Model in CAISER

Keun Sang Choi (KAERI), Jun-young Kang (KAERI), Donggun Son (KAERI), Jun-Ho Bae (KAERI)

Three-Dimensional CFD Analysis of PHWR Exposed Core Under Postulated Severe Accident Condition

S. Rajaganesh (Homi Bhabha National Institute), Deb Mukhopadhyay (Homi Bhabha National Institute)

Three-Phase Flow Simulation of Debris Bed Self-Leveling in case of SFR Severe Accident

Cyriaque Treol (CEA), Rémi Clavier (CEA), Nathalie Seiler (CEA), Benoit Goyeau (Ecole Centrale-Supelec)

New Correlations for Focusing Effect Evaluation of the Light Metal Layer in the Lower Head of a Nuclear Reactor in Case of Severe Accident

F. Rein (IRSN), F. Fichot (IRSN), L. Carénini (IRSN), M. Le Bars (Aix Marseille Univ.), B. Favier (Aix Marseille Univ.)

Investigation of Reynolds Stress Models for RANS of Natural Convection of a Corium Pool for in-Vessel Retention

D. Dovizio (Nuclear Research & Consultancy Group)

Dryout Modeling Based on Interfacial Shear Stress of Gas-Liquid Flow

Cheng Peng (Shanghai Univ. Electric Power), Helin Chen (Shanghai Univ. Electric Power), Dong Li (Shanghai Univ. Electric Power)

Coolability of a Corium Pool in a Debris Bed -- Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

C. Sartoris (IRSN), T. Garcin (IRSN), F. Fichot (IRSN)

Preliminary Study on Melt Spreadability in Ex-Vessel Core Catcher Under Dry Condition

Byung Jo Kim (KEPCO Engineering and Construction Co.), Dae Hyung Lee (KEPCO Engineering and Construction Co.), Sun Hong Yoon (KEPCO Engineering and Construction Co.)

Analysis of Corium Coolability in MCCI Conditions for Two Types of Concrete, Using ASTEC Calculations

C. Bouillet (IRSN)

Simplified Model for One-Dimensional Ex-Vessel Corium Coolability

Jaehoon Jung (KAERI), Seokgyu Jeong (KAERI)

Transient Cooling Investigation of a Conceptual Core Catcher Design with Embedded Cooling Tubes Using a GOTHIC 3D Model

Zhuo Liu (China Nuclear Power Engineering Co.), Wei Li (China Nuclear Power Engineering Co.), Qiang Guo (China Nuclear Power Engineering Co.), Yidan Yuan (China Nuclear Power Engineering Co.), Ningxi Jia (China Nuclear Power Engineering Co.), Yu Jin (China Nuclear Power Engineering Co.), Weimin Ma (Royal Institute of Technology)

Determination of Effective Heat Transfer Coefficients Using the Decomposition Parameters of Silicate Concrete, the Melt Composition, and the Heating Power with AC²-COCOSYS

Maximilian Hoffmann (Ruhr Univ. Bochum), Marco K. Koch (Ruhr Univ. Bochum)

The Role of Zr-Oxidation During Molten Core-Concrete Interaction

Xiaoyang Gaus-Liu (Karlsruhe Institute of Technology)

Mesh Sensitivity Analysis of the CFD Model of the Core Catcher of the ALLEGRO Reactor

Jan Komrska (Czech Technical Univ. Prague), Pavel Zacha (Czech Technical Univ. Prague), Petr Vacha (UJV Rez)

Steam Explosion Retardant for Long-Term Coolability

Masahiro Furuya (Waseda Univ.), Takahiro Arai (CRIEPI)

Thermodynamic Calculation Methodology of Specifically Designed Sacrificial Material for Ex-Vessel Core Catcher

Erhui Chen (China Nuclear Power Engineering Co.), Li Zhang (China Nuclear Power Engineering Co.), Nan Li (China Nuclear Power Engineering Co.), Xiao Zeng (China Nuclear Power Engineering Co.), Qiang Guo (China Nuclear Power Engineering Co.), Yidan Yuan (China Nuclear Power Engineering Co.), Xiao-Gang Lu (Shanghai Univ.), Yeqing Ding (Shanghai Univ.)

Analysis of Hydrogen Diffusion Ignition in Oxygen-Nitrogen Mixtures

Odai Nassar (Tel Aviv Univ.), Surya Kaundinya Oruganti (Tel Aviv Univ.), Marcel Martins Alves (Tel Aviv Univ.), Sergey Kudriakov (CEA), Etienne Studer (CEA), Liel Ishay (Nuclear Research Center Negev), Yoram Kozak (Tel Aviv Univ.)

PANDA Experiment Addressing the Thermal Effects in a Large Water Pool Caused by Steam and a Lighter Non-condensable Gas Release from a Multi-Hole Sparger

Domenico Paladino (Paul Scherrer Institute), Ralf Kapulla (Paul Scherrer Institute), Myeong Seon Chae (Paul Scherrer Institute), Sidharth Paranjape (Ostschweizer Fachhochschule), Guillaume Mignot (Oregon State), Pavel Kudinov (Royal Institute of Technology)

Recombination of Hydrogen and Carbon Monoxide on Silver-Based Zeolites in the Presence of Steam and at Pressures up to 3 Bar

J. Mantzaras (Paul Scherrer Institute), V.K. Arumugam (Paul Scherrer Institute), J. Theile (Paul Scherrer Institute), D. Suckow (Paul Scherrer Institute), F. Espegren (Paul Scherrer Institute), T. Lind (Paul Scherrer Institute)

Experiments on the Impact of Carbon Monoxide on the Efficiency of Catalysts used for Hydrogen Mitigation in the Late Phase of a Severe Accident

Ernst-Arndt Reinecke (Forschungszentrum Juelich), Gabriela Nobrega (IRSN), Michael Klauck (Forschungszentrum Jülich)

Influence of Iodine Chemistry in I2 Scrubbing Modeling

Adolf Rydl (INSET), Taizo Kanai (Central Research Institute of Electric Power Industry)

Analyses of Jet-Buoyant Flow in a Multi-Compartment Containment Using an Open-Source Solver

Myeong-Seon Chae (Paul Scherrer Institute), Domenico Paladino (Paul Scherrer Institute), Stephan Kelm (Forschungszentrum Juelich)

The SAAB Project: Experimental Studies on Several Phenomena Related to the Assessment of Aerosol Behavior in Severe Accidents

Michael Klauck (Forschungszentrum Jülich), Yihui Wu (Forschungszentrum Jülich), Rene Vennemann (Ruhr-Univ. Bochum), Hans-Josef Allelein (RWTH Aachen Univ.)

Main Outcomes of OECD/NEA THAI-2 Project and its Use for Code Validation and Containment Safety Assessment Under Accident Conditions

S. Gupta (Becker Technologies), M. Freitag (Becker Technologies), Z. Liang (Canadian Nuclear Laboratories), F. Funke (Framatome), G. Langrock (Framatome), S. Beck (GRS), H. Nowack (GRS), A. Bentaib (IRSN), L. Cantrel (IRSN), J. Ishikawa (Japan Atomic Energy Agency), S.W. Hong (KAERI), P. Kostka (Nuclear Safety Research Institute), J. Glover (Office for Nuclear Regulation), C. Linde (Swedish Radiation Safety Authority), M. Kotouč (ÚJV Řež), V. Taivassalo (VTT Technical Research Centre)

Sensitivity Analysis of Consequential Steam Generator Tube Rupture (C-SGTR) of Typical Korean NPP

Byeonghee Lee (KAERI), Jin Ho Song (KAERI), Kwang Soon Ha (KAERI)

A Methodology for Real-Time Identification of a PWR Accident and Predictive Analysis

Paul McMinn (Fauske & Assoc.), Nick Karancevic (Fauske & Assoc.), Chan Y. Paik (Fauske & Assoc.), Wei Wei (China Nuclear Power Operation Technology Corp.), Ma Guoyang (China Nuclear Power Operation Technology Corp.)

Hysteresis Impacts in Steady Flow Transitions of the Rayleigh Bénard Problem with Internal Heating; Implications on Heat Transfer Margin in External Reactor Vessel Cooling Strategies

A. Lentner (George Washington Univ.), E. Balaras (George Washington Univ.)

Source Term Uncertainty Analysis of Severe Accidents in Nordic BWRs

Govatsa Acharya (Royal Institute of Technology), Ioannis Komlikis (Royal Institute of Technology), Dmitry Grishchenko (Royal Institute of Technology), Pavel Kudinov (Royal Institute of Technology), Sergey Galushin (Vysus Group)

Experimental Investigation on the Depletion Behavior of Multi-Component Aerosols

Yihui Wu (RWTH Aachen Univ.), Michael Klauck (Forschungszentrum Jülich), Hans-Josef Allelein (RWTH Aachen Univ.)

Theoretical Investigation of the Shock-Tube Diaphragm Influence on Pressurized-Hydrogen Jet Release Ignition Limits

Marcel Martins Alves (Tel Aviv Univ.), Odai Nassar (Tel Aviv Univ.), Sergey Kudriakov (CEA), Etienne Studer (CEA), Liel Ishay (Nuclear Research Center Negev), Yoram Kozak (Tel Aviv Univ.)

A Numerical Study for Modeling Sprays in TOSQAN-101 Experiment Using OpenFOAM

Keun Sang Choi (KAERI), Jaehoon Jung (KAERI), Gun-Hong Kim (OpenCAE)

Ensuring Comparability of Measured Results in Aerosol-Related Experiments: Exemplary Approach Using Experiments on Water-Induced Particle Retention

Hans-Josef Allelein (RWTH Aachen Univ.), Michael Klauck (Forschungszentrum Jülich), Kathrin Trollmann (Forschungszentrum Juelich), Yihui Wu (Forschungszentrum Juelich), Rene Vennemann (Ruhr-Univ. Bochum)

Comparison Between EDF MAAP5.04, EPRI MAAP5.06 and CATHARE Codes on Hypothetical Accidental Transients Leading to a Core Damage on the NUWARD SMR Design

Jeremy Bittan (EDF)

The iPWR MELCOR 2.2 Parametric Sensitivity Analysis

Mateusz Malicki (Paul Scherrer Institute), Piotr Darnowski (Warsaw Univ. Technology), Terttaliisa Lind (Paul Scherrer Institute)

Analyses of the MELCOR Capability to Simulate Integral PWR Using Passive Systems

F. Giannetti (Sapienza Univ. Rome), M. Imperatori (Sapienza Univ. Rome), M. D'Onorio (Sapienza Univ. Rome), M. Garcia (CIEMAT), L. E. Herranz (CIEMAT), A. Bersano (ENEA), F. Mascari (ENEA)

Advanced FCVS System Using Silver Zeolite AgX, AgR and XeA

Yoshihiro Ishikawa (Rasa Industries), Koji Endo (Rasa Industries), Tadashi Narabayashi (Tokyo Institute of Technology), D. Suckow (Paul Scherrer Institute), F. Espegren (Paul Scherrer Institute), T. Lind (Paul Scherrer Institute), J. Mantzaras (Paul Scherrer Institute), V.K. Arumugam (Paul Scherrer Institute), J. Theile (Paul Scherrer Institute), Yuta Nakasaka (Hokkaido Univ.), Yasuhiro Kawahara (Kimura Chemical Plants Co.)

Sensitivity Analysis of Heat Transfer Limit Under IVR-ERVC Condition Based on a Newly Developed CHF Model

Gang Wang (Shanghai Jiao Tong Univ.), Shilei Han (Shanghai Jiao Tong Univ.), Bo Kuang (Shanghai Jiao Tong Univ.), Pengfei Liu (Shanghai Jiao Tong Univ.)

The SAIGA In-Pile Experimental Test to Study the Degradation of a SFR Core with Mitigation Devices in Severe Accident Conditions

F. Payot (CEA), F. Charollais (CEA), E. Dufour (CEA), Y. Lejeail (CEA), G. Blevin (CEA), L. Trotignon (CEA), G. De Izarra (CEA), F. Michel (CEA), V. Dupont (CEA), N. Chikhi (CEA), R. Clavier (CEA), E. Batyrbekov (National Nuclear Center of the Republic of Kazakhstan), A. Vurim (National Nuclear Center of the Republic of Kazakhstan), A. Pakhnits (National Nuclear Center of the Republic of Kazakhstan), V. Baklanov (National Nuclear Center of the Republic of Kazakhstan)

Canadian Nuclear Laboratories Experiments and Modeling of Water-Cooled SMR Severe Accidents to Inform Level 4 and 5 Defence-in-Depth

Luke Lebel (Canadian Nuclear Laboratories), Andrew Morreale (Canadian Nuclear Laboratories), Eric Jia (Canadian Nuclear Laboratories), Feng Zhou (Canadian Nuclear Laboratories), David Hummel (Canadian Nuclear Laboratories), Scott Ormiston (Univ. Manitoba), Geoffrey Gray (Univ. Manitoba)

Preliminary Analysis of Severe Accident in Sodium-Cooled Fast Reactor Using Eutectic Reaction Model of Boron-Carbide Control-Rod Material

Hidemasa Yamano (Japan Atomic Energy Agency), Koji Morita (Kyushu Univ.)

Application of Artificial Neural Network to Identify Severe Accident State from Plant Signal Data

Paul McMinn (Fauske and Assoc.), Nick Karancevic (Fauske and Assoc.), Chan Y. Paik (Fauske and Assoc.), Wei Wei (China Nuclear Power Operation Technology Corp.), Ma Guoyang (China Nuclear Power Operation Technology Corp.)

Simulating the Power Noise Response due to Voiding in the NBSR During the February 3rd Incident

Lap-Yan Cheng (Brookhaven), Athi Varuttamaseni (Brookhaven), Peter Kohut (Brookhaven), Anil Gurgen (Nat'l Institute of Standards & Technology), Dagistan Sahin (Nat'l Institute of Standards & Technology), Abdullah G. Weiss (Nat'l Institute of Standards & Technology)

Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis

M. Garbarini (Politecnico di Milano), G. Agnello (Univ. Palermo), A. Bersano (ENEA), F. Gabrielli (Karlsruhe Institute for Technology), L. Luzzi (Politecnico di Milano), F. Mascari (ENEA)

Evaluation of Accident Tolerant Fuel Performance Under Long-Term Station Blackout Conditions

Chris Faucett (Sandia), Bradley Beeny (Sandia), Jesse Phillips (Sandia), Karen Vierow Kirkland (TAMU)

Application of Lower Head Thermal-Mechanical Creep Failure Module in LHF Experiment

Hao Yang (Xi'an Jiaotong Univ.), Bin Zhang (Xi’an Jiaotong Univ.), Pengcheng Gao (Xi’an Jiaotong Univ.), Jianqiang Shan (Xi’an Jiaotong Univ.)

Validation in Water of a New Methodology for the Vibrational Analysis of Rotating Components in a High-Density Fluid

Kamiel Ceusters (Ghent Univ.), Michiel Van Damme (Ghent Univ.), Henri Dolfen (Ghent Univ.), Nicolas Delaissé (Ghent Univ.), Tom Verstraete (Ghent Univ.), Joris Degroote (Ghent Univ.), Kirill Makhov (SCK CEN), Mikhail Iarmonov (SCK CEN), Katrien Van Tichelen (SCK CEN)

Sensor Selection for the Measurement of Fuel Plate Deflections

Michael Legatt (Oregon State), Aaron Weiss (Oregon State), Trevor Kent Howard (Oregon State), Wade Marcum (Oregon State), Cezary Bojanowski (ANL), Guanyi Wang (ANL), Andrew Hebden (ANL)

Fluid-Structure Interaction Analysis of University of Missouri Research Reactor Low-Enriched Uranium Fuel Element

Guanyi Wang (ANL), Cezary Bojanowski (ANL), Wilson Cowherd (ANL), Walid Mohamed (ANL), Erik Wilson (ANL), Maria Pinilla (University of Missouri-Columbia Research Reactor)

PWR Nuclear Fuel Rod Flow Induced Vibration Simulation Using VITRAN Code for Hexagonal Fuel Assembly

Alireza Mofidi (Westinghouse Electric Co.), Roger Y. Lu (Westinghouse Electric Co.)

Building a Multiscale Framework: An Overview of the NEAMS Thermal-Hydraulics Integrated Research Project

Elia Merzari (Penn State), Arsen Iskhakov (NCSU), Igor Bolotnov (NCSU), Nam Dinh (NCSU), Emilio Baglietto (MIT), Annalisa Manera (Univ. Michigan), Dillon Shaver (ANL), Yassin Hassan (TAMU)

NEAMS IRP Challenge Problem 1: Flexible Modeling for Heat Transfer for Applications in Advanced Reactors

Igor A. Bolotnov (NCSU), Arsen S. Iskhakov (NCSU), Tri Nguyen (Penn State), Cheng-Kai Tai (NCSU), Ralph Wiser (MIT), Emilio Baglietto (MIT), Nam Dinh (NCSU), Dillon Shaver (ANL), Elia Merzari (Penn State)

NEAMS IRP Challenge Problem 2: Thermal Striping of Reactor Internals

Emilio Baglietto (MIT), John Acierno (Penn State), Annalisa Manera (Univ. Michigan), Quynh M. Nguyen (Univ. Michigan), Victor Petrov (Univ. Michigan), Monica Pham (MIT), Yu-Jou Wang (MIT), Yue Jin (MIT), Jinyong Feng (MIT), Wayne Strasser (Liberty Univ.), Dillon Shaver (ANL), Elia Merzari (Penn State)

NEAMS IRP Challenge Problem 3: Mixing in Large Enclosures and Thermal Stratification

A. Manera (Univ. Michigan), A.S. Iskhakov (NCSU), V.C. Leite (Penn State), Jiaxin Mao (Univ. Michigan), C. Tai (NCSU), V. Vishwakarma (Univ. Michigan), R. Wiser (MIT), E. Baglietto (MIT), I.A. Bolotnov (NCSU), N.T. Dinh (NCSU), Y. Hassan (TAMU), V. Petrov (Univ. Michigan), E. Merzari (Penn State)

Challenge Problem 4: Building a Flexible Multiscale Framework for Core Modeling

Yassin Hassan (TAMU), Craig Menezes (TAMU), David Reger (Penn State), Adam Kraus (Penn State), Elia Merzari (Penn State)

Machine-Learning-Aided Approach for Predicting the Thermal Expansion Behaviors in Advanced Test Reactor Capsules

Takanori Kajihara (INL), Han Bao (INL), Nicolas E. Woolstenhulme (INL), Colby B. Jensen (INL), Daniel B. Chapman (INL), Sunming Qin (INL), Austin D. Fleming (INL)

Investigation of Machine Learning Regression Techniques to Predict Critical Heat Flux over a Large Parameter Space

Emil Helmryd Grosfilley (Uppsala Univ.), Gustav Robertson (Uppsala Univ.), Jerol Soibam (Mälardalen Univ.), Jean-Marie Le Corre (Westinghouse Electric Sweden)

Using Machine Learning to Assess Spill Fire Data for use in Fire PRA

Elvan Sahin (Virginia Tech), Mehran Islam (Virginia Tech), Brian Y. Lattimer (Virginia Tech), Juliana P. Duarte (Univ. Wisconsin, Madison)

Machine Learning from LES Data to Improve Coarse Grid RANS Simulations

Arsen S. Iskhakov (NCSU), Taylor Grubbs (NCSU), Nam T. Dinh (NCSU), Victor Coppo Leite (Penn State), Elia Merzari (Penn State)

Fully Implicit Conjugate Heat Transfer Analysis of the ARC-Class Vacuum Vessel

Arpan Sircar (ORNL), Katarzyna Borowiec (ORNL), Jin Whan Bae (ORNL), Vittorio Badalassi (ORNL), Jerome Solberg (LLNL)

Design and Analysis of a Novel Molten Salt Fusion Breeder Blanket System Using SAM

Trevor C. Franklin (Virginia Commonwealth Univ.), Ryan P. McGuire (Virginia Commonwealth Univ.), Amelie M. Lutz (Virginia Commonwealth Univ.), Sierra A. Tutwiler (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.)

Simulations of Heat Transfer Using Tight Fitting Twisted Tape Inserts for 1st Wall Cooling in Molten Salt Breeder Blankets

Sierra Tutwiler (Virginia Commonwealth Univ.), Ryan P. McGuire (Virginia Commonwealth Univ.), Trevor C. Franklin (Virginia Commonwealth Univ.), Amelie M. Lutz (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.), Carter E. Steward (Virginia Military Institute)

Thermal Hydraulic and Mechanical Assessment of the DTT ICRH Antenna

Ranieri Marinari (ENEA), Pietro Maccari (ENEA), Alessandro Del Nevo (ENEA), Nicolò Badodi (Politecnico di Milano), Silvio Ceccuzzi (ENEA), Gianluca Camera (Università degli Studi di Napoli Federico II), Giuseppe Di Gironimo (Università degli Studi di Napoli Federico II)

The European GO-VIKING Project on Flow-Induced Vibrations

A. Papukchiev (GRS), K. Zwijsen (Nuclear Research & Consultancy Group), D. Vivaldi (IRSN), H. Hadzic (Framatome), S. Benhamadouche (EDF R&D), W. Benguigui (EDF R&D), P. Planquart (von Karman Institute for Fluid Dynamics)

Wall-Resolved LES and URANS Simulations of an Axial Flow on a Cantilevered Rod at a Moderate Reynolds Number

Thomas Norddine (EDF R&D), Sofiane Benhamadouche (EDF R&D)

Experiments on Axial-Flow-Induced Vibration of a Free-Clamped Rod for Light Water Nuclear Reactor Applications

Hao Li (Univ. Manchester), Shanying Zhang (Univ. Manchester), Mostafa R.A. Nabawy (Univ. Manchester), Hector Iacovides (Univ. Manchester), Andrea Cioncolini (Guangdong Technion-Israel Institute of Technology)

Numerical Simulation of Flow-Induced Vibration of Nuclear Fuel Assemblies

H. Hadzic (Framatome), M. Ren (Framatome), B. Dressel (Framatome), D. Tumbajoy Spinel (Framatome), M. Quenehen (Framatome), B. Painter (Framatome), H. Marr (Framatome), K. Duggan (Framatome)

Development of an Anisotropic Pressure Fluctuation Model for the Prediction of Turbulence-Induced Vibrations of Fuel Rods

K. Zwijsen (Nuclear Research & Consultancy Group), N. van den Bos (Nuclear Research & Consultancy Group), E.M.A. Frederix (Nuclear Research & Consultancy Group), F. Roelofs (Nuclear Research & Consultancy Group), A.H. van Zuijlen (Delft Univ. Technology)

Wall-Resolved LES and Low-Reynolds Number URANS Combined to an Arbitrary Lagrangian Eulerian Approach for Predicting Water Cross-Flow Induced Vibrations of a Single Flexible Tube in a Normal Square Tube Array

Sofiane Benhamadouche (EDF R&D), William Benguigui (EDF R&D)

Modeling of Flow-Induced Vibrations of a BWR Instrumentation Guide Tube Experiment

K. Zwijsen (Nuclear Research & Consultancy Group), S. Tajfirooz (Nuclear Research & Consultancy Group), F. Roelofs (Nuclear Research & Consultancy Group), A. Papukchiev (GRS), N. Edh (Vattenfall), E. Lillberg (Vattenfall)

URANS and Hybrid URANS/LES Coupled Fluid-Structure Simulations of Fluid-Induced Vibrations in a Square-Pitch Tube Bundle Subjected to Water Cross-Flows

Daniele Vivaldi (IRSN), Jean Baccou (IRSN)

Lead Fast Reactor Thermal Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program

J. Liao (Westinghouse Electric Co.), C. A. Stansbury (Westinghouse Electric Co.), M. E. Durse (Westinghouse Electric Co.), D. L. Wise (Westinghouse Electric Co.), E. Tatli (Westinghouse Electric Co.), T. G. Loebig (Westinghouse Electric Co.), R. F. Wright (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), S.J. Lee (Fauske & Assoc.), M. Epstein (Fauske & Assoc.), M. Caramello (Ansaldo Nucleare), M. Frignani (Ansaldo Nucleare), M. Tarantino (ENEA), G. Grasso (ENEA), I. Di Piazza (ENEA), S. Bassini (ENEA), P. Lorusso (ENEA), A. Antonelli (ENEA), D. Martelli (ENEA), A. Wimshurst (Frazer-Nash Consultancy), R. Watkins (Frazer-Nash Consultancy), G. Macpherson (Frazer-Nash Consultancy), D. Wilson (Univ. Manchester), H. Iacovides (Univ. Manchester), A. Cioncolini (Univ. Manchester), J. Francis (Univ. Manchester), J. Buckley (Univ. Manchester)

Evaluation of Steam Explosion in the Lead-Water Interaction Test Facility for Westinghouse Lead Fast Reactor Development

M. Epstein (Fauske & Assoc.), S.J. Lee (Fauske & Assoc.), M. Tarantino (ENEA), F. Hattab (ENEA), P. Ferroni (Westinghouse Electric Co.)

Testing Innovative Decay Heat Removal System Through the Passive Heat Removal Facility (PHRF): Facility Description and Early Testing in Support to Lead Fast Reactor Development

M. Caramello (Ansaldo Nucleare), M. Frignani (Ansaldo Nucleare), A. Cocucci (Ansaldo Nucleare), M. Tarantino (ENEA), J. Liao (Westinghouse Electric Co.), R.F. Wright (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.)

Testing Key Lead Fast Reactor Components Through the Versatile Loop Facility (VLF): Facility Description and Early Testing in Support to Lead Fast Reactor Development

M. Caramello (Ansaldo Nucleare), M. Frignani (Ansaldo Nucleare), A. Cocucci (Ansaldo Nucleare), M. Tarantino (ENEA), C. Stansbury (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.)

Main Outputs from the OECD/NEA ARC-F Project

Yu Maruyama (Japan Atomic Energy Agency), Tomoyuki Sugiyama (Japan Atomic Energy Agency), Asako Shimada (Japan Atomic Energy Agency), Terttaliisa Lind (Paul Scherrer Institute), Ahmed Bentaib (IRSN), Martin Sogalla (GRS), Marco Pellegrini (Univ. Tokyo), Lucas Albright (Sandia), Daniel Clayton (Sandia)

OECD/NEA ARC-F Project: Summary of Fission Product Transport

Terttaliisa Lind (Paul Scherrer Institute), Jarmo Kalilainen (Paul Scherrer Institute), Catherine Marchetto (IRSN), Sara Beck (GRS), Koichi Nakamura (CRIEPI), Chiaki Kino (IAE), Yu Maruyama (Japan Atomic Energy Agency), Kentaro Kido (Japan Atomic Energy Agency), Sung Il Kim (KAERI), Yoonhee Lee (KINS), Luis E. Herranz (CIEMAT), Kirill Dolganov (IBRAE)

OCDE/NEA-ARC-F Project: Unit1 and Unit3 Hydrogen Explosion Analysis -- Lessons Learned and Perspectives

A. Bentaib (IRSN), A. Bleyer (IRSN), E. Studer (CEA), S. Kudriakov (CEA), T. Nishimura (NRA), K. Motegi (Japan Atomic Energy Agency), K.S. Dolganov (IBRAE RAN)

Analysis of the Long Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1

M. Pellegrini (Univ. Tokyo), C. Journeau (CEA), N. Seiler (CEA), L.E. Herranz (CIEMAT), C. Spengler (GRS), C. Bouillet (IRSN), M. Barrachin (IRSN), D. Luxat (Sandia), L. Albright (Sandia)

GOTHIC Thermal Hydraulic Analysis of the Passive Heat Removal Facility to Support the Westinghouse Lead Fast Reactor Development

M.E. Durse (Westinghouse Electric Co.), D.L. Wise (Westinghouse Electric Co.), J. Liao (Westinghouse Electric Co.), R.F. Wright (Westinghouse Electric Co.), C.A. Stansbury (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), M. Caramello (Ansaldo Nucleare), A. Wimshurst (Frazer-Nash Consultancy)

Numerical Analysis and Codes Qualification Based on SIRIO Experiments Within the PIACE Project

P. Lorusso (ENEA), M. Tarantino (ENEA), F.S. Nitti (ENEA), A. Achilli (SIET), M. Cauzzi (SIET), M. Caramello (Ansaldo Nucleare), T. Hamidouche (SCK CEN), R. Fernandez (SCK CEN), D. Rozzia (SCK CEN), I. Kljenak (Jozef Stefan Institute), R. Krpan (Jozef Stefan Institute), G. Jimenez (Univ. Politécnica de Madrid), C. Queral (Univ. Politécnica de Madrid), T. Del Moro (Sapienza Univ. Rome)

Analysis of Steady State and Operational Transients of the Versatile Loop Facility in Support to Lead Fast Reactor Development

C. Ciurluini (Sapienza Univ. Rome), M. Principato (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), M. Caramello (Ansaldo Nucleare), M. Tarantino (ENEA)

Application Development and Verification of Lead Cooling System Safety Analysis Program based on RELAP5 MOD4.0

Xiangyang Wang (Lanzhou Univ.), Liu Yang (Lanzhou Univ.), Su Xingkang (Lanzhou Univ.), Qijian Chen (Lanzhou Univ.), Lu Zhang (Chinese Academy of Science), Xianwen Li (Chinese Academy of Science), Bin Han (Southeast Univ.), Aiguo Liu (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Gu Long (Lanzhou Univ.)

Source Term Reconstruction Within the ARC-F Project

Martin Sogalla (GRS), Sara Beck (GRS), Johannes Martens (GRS), Olivier Saunier (IRSN), Shogo Takahara (Japan Atomic Energy Agency)

The Round Robin Debris Analysis Activity Conducted Under the OECD-NEA FACE Project

Andrew C. Morreale (Canadian Nuclear Laboratories), Mitchell T. Farmer (ANL), Joy Rempe (Rempe and Assoc.), Christophe Journeau (CEA), Damian Peko (U.S. Dept. of Energy)

CFD Modelling of Lead Solidification and Natural Convection for the Westinghouse Lead-Cooled Fast Reactor

D. Wilson (Univ. Manchester), H. Iacovides (Univ. Manchester), E. Tatli (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), S.J. Lee (Fauske & Assoc.)

CFD and STH Thermal-Hydraulic Analyses in Support of the CIRCE-THETIS Experimental Campaign

P. Stefanini (Univ. Pisa), A. Pucciarelli (Univ. Pisa), N. Forgione (Univ. Pisa), I. Di Piazza (ENEA Brasimone R.C.)

CFD Analysis of the Passive Heat Removal System in the Conceptual Design Phase of the Westinghouse Lead-Cooled Fast Reactor Under Air Cooling Conditions

Aidan Wimshurst (Frazer-Nash Consultancy), Graham Macpherson (Frazer-Nash Consultancy), Rhodri Watkins (Frazer-Nash Consultancy), Carolyn Howlett (Frazer-Nash Consultancy), Jun Liao (Westinghouse Electric Co.), Emre Tatli (Westinghouse Electric Co.), Cory Stansbury (Westinghouse Electric Co.), Megan Durse (Westinghouse Electric Co.), Richard Wright (Westinghouse Electric Co.), Marco Caramello (Ansaldo Nucleare)

Thermal-Hydraulic Analysis of a Representative Westinghouse Lead-Cooled Fast Reactor Fuel Bundle Using CFD

D. Wilson (Univ. Manchester), H. Iacovides (Univ. Manchester), E. Tatli (Westinghouse Electric Co.), C. Stansbury (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.)

Prediction of Departure from Nucleate Boiling Power Using ANN and PIML Algorithms

Chaitee Godbole (NCSU), Gregory Delipei (NCSU), Xu Wu (NCSU), Maria Avramova (NCSU), Upendra Rohatgi (Brookhaven)

Deep Generative Modeling for Augmentation of the Steady-State Void Fraction Dataset in the BFBT Benchmark

Farah Alsafadi (NCSU), Xu Wu (NCSU)

Data-Driven RANS Turbulence Modeling of Mixed Convection in Reactor Downcomer Geometry

Arsen S. Iskhakov (NCSU), Cheng-Kai Tai (NCSU), Igor A. Bolotnov (NCSU), Nam T. Dinh (NCSU), Elia Merzari (Penn State)

Data-Driven Augmentation of a Second Order Heat Flux Model to Extend it to Heavy Liquid Metals

Matilde Fiore (von Karman Institute for Fluid Dynamics), Lilla Koloszar (von Karman Institute for Fluid Dynamics), Miguel Alfonso Mendez (von Karman Institute for Fluid Dynamics), Matthieu Duponcheel (Univ. Catholique de Louvain), Yann Bartosiewicz (Univ. Catholique de Louvain)

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

V. Habiyaremye (Nuclear Research & Consultancy Group), A. Mathur (Nuclear Research & Consultancy Group), F. Roelofs (Nuclear Research & Consultancy Group)

Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at Forced Circulation and Under Isothermal Conditions

F. S.L. Pangukir (Nuclear Research & Consultancy Group), D. C. Visser (Nuclear Research & Consultancy Group), F. Roelofs (Nuclear Research & Consultancy Group), J. Pacio (SCK CEN), K. Van Tichelen (SCK CEN)

Review on Heat Transfer Performance of High Temperature Heat Pipe

Haojie Zhang (Beijing Jiaotong Univ.), Zhuqian Zhang (Beijing Jiaotong Univ.), Lixin Yang (Beijing Jiaotong Univ.)

Direct Numerical Simulation of Liquid Metal Forced and Mixed Convection in a Square Rod Bundle

Diego Angeli (Univ. Modena and Reggio Emilia), Danila Trane (Univ. Modena and Reggio Emilia), Andrea Cimarelli (Univ. Modena and Reggio Emilia), Roberto Corsini (Univ. Modena and Reggio Emilia), Enrico Stalio (Univ. Modena and Reggio Emilia)

Digital Twin Development for Advanced Reactor System Based on Graph Neural Networks Using SAM Code Simulation

Yang Liu (ANL), Farah Alsafadi (NCSU), Travis Mui (ANL), Daniel O'Grady (ANL), Rui Hu (ANL)

Introducing the OECD/NEA WPRS Benchmark on Artificial Intelligence and Machine Learning for Scientific Computing in Nuclear Engineering

Xu Wu (NCSU), Gregory Delipei (NCSU), Maria Avramova (NCSU), Kostadin Ivanov (NCSU), Oliver Buss (OECD/NEA)

Application of a Physics-Informed Convolutional Neural Network for Temperature Field Monitoring in Advanced Reactors

Victor Coppo Leite (Penn State), Elia Merzari (Penn State), April Novak (ANL), Roberto Ponciroli (ANL), Lander Ibarra (ANL)

Prediction of Turbulent Flow Regime Boundary and Pressure Drop for Hexagonal Wire-Wrapped Rod Assemblies Using Artificial Neural Networks

Hansol Kim (TAMU), Joseph Seo (TAMU), Yassin A. Hassan (TAMU)

Physics-Informed Forecasting of NPPs Operating Parameters Using Machine Learning

Houde Song (Shanghai Jiao Tong Univ.), Meiqi Song (Shanghai Jiao Tong Univ.), Yanjie Tuo (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.)

Flow Regime Classification Using Orientation-Independent Layered Spectral Clustering

David Kang (Purdue), Drew Ryan (Purdue), Seungjin Kim (Purdue)

Preliminary Analysis of the Effects of Alumina Nanofluids on Critical Heat Flux Using Artificial Intelligence

Bruno Pinheiro Serrao (Univ. Wisconsin, Madison), Juliana Pacheco Duarte (Univ. Wisconsin, Madison)

Application of Structure-Based Machine Learning Model on Thermal Striping Evaluation

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

Reduced-Order Model of Flow Field in Nuclear Power System Based on POD and Deep Learning

Jun Yang (Nuclear Power Institute of China), Yanping Huang (Nuclear Power Institute of China), Dianle Wang (Nuclear Power Institute of China), Ling Zhao (Nuclear Power Institute of China), Yong Li (Nuclear Power Institute of China)

A Platform for a Machine Learning Diagnosis of the Severe Accident

JinHo Song (Hanyang Univ.), SungJung Kim (Hanyang Univ.)

Once-Through Steam Generator Health Management Based on Adaptive Relevance Vector Machine: Remaining Useful Life Prediction

Mudi Jiang (Southeast Univ.), Tianyang Xing (Southeast Univ.), Bin Han (Southeast Univ.), Junlin Huang (Southeast Univ.), Shenghui Liu (Southeast Univ.), Xiaoliang Zhu (Southeast Univ.)

Economic Evaluation of Electricity Supply and Storage in Energy Poor Region Using Microreactor and Two-Step Water Splitting Method

SeockYong Lee (Pohang Univ. Science and Technology), Su Won Lee (Pohang Univ. Science and Technology), UngJin Na (Pohang Univ. Science and Technology), HangJin Jo (Pohang Univ. Science and Technology)

Integrated Energy System Model in OpenModelica for Producing Energy, Powering a Desalination Plant and for District Heating

Md Akhlak Bin Aziz (Univ. Illinois, Urbana-Champaign), Caleb Brooks (Univ. Illinois, Urbana-Champaign), CT Callaway (Univ. Tennessee, Knoxville), Nicholas Brown (Univ. Tennessee, Knoxville)

Data Projection of the High Temperature Electrolysis System in the Dynamic Energy Transport and Integration Laboratory Using Dynamic System Scaling

Ramon Yoshiura (INL), Jiangkai Peng (INL), Aaron Epiney (INL)

Partial Arc Admission in an SMR Steam Turbine to Improve Load Following: Model Benchmark, Thermal-Hydraulic Mechanism Analysis and Application Case in a Full Rankine Cycle

G. Vescovi (CEA), N. Alpy (CEA), D. Haubensack (CEA), C. Azzaro-Pantel (Univ. Toulouse), P. Stouffs (Univ. Pau et des Pays de l'Adour), A. Charvet (Institut National des Sciences Appliquées de Lyon)

Deep Learning Based Thermal Performance Optimization for the Liquid Metal Heat Pipe

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

Coarse-Grid Data-Driven Navier-Stokes / Interface Capturing Model Development for Engineering-Scale Simulations

Anna Iskhakova (NCSU), Arsen S. Iskhakov (NCSU), Yoshiyuki Kondo (Mitsubishi Heavy Industries), Koichi Tanimoto (Mitsubishi Heavy Industries), Nam T. Dinh (NCSU), Igor A. Bolotnov (NCSU)

Multi-Objective Optimization of Fractal-Tree Microchannels for Printed Circuit Heat Exchangers by Improved Genetic Algorithms

Fan Yu (Helmholtz-Zentrum Dresden-Rossendorf), Wei Ding (Helmholtz-Zentrum Dresden-Rossendor), Sebastian Unger (Helmholtz-Zentrum Dresden-Rossendorf), Xiaoping Luo (South China Univ. Technology), Uwe Hampel (Helmholtz-Zentrum Dresden-Rossendorf)

Machine Learning Anomaly Data Detection and Accident Diagnosis Methodology Using MARS-KS Design Basis Event Analysis Database of APR1400 Nuclear Power Plant

J.Y. Lee (Environment & Energy Technology), S.M. Park (Environment & Energy Technology), Y.K. Kwack (Environment & Energy Technology), Y.S. Kim (Environment & Energy Technology), N.H. Hoang (Environment & Energy Technology), S.K. Sim (Environment & Energy Technology)

Validation on SBLOCA Experiment of the ACME Test Facility Using the ATHLET Code

Liancheng Guo (GRS), Thorsten Hollands (GRS), Henrique Austregesilo (GRS)

Assessment of the CATHARE Code over SUPERCLAUDIA Tests for a Jet in a Liquid Water Pool

Angela Oliva (CEA), Sofia Carnevali (CEA), Franck Morin (CEA), Stephane Mimouni (EDF)

Simulation of Oscillatory Flow Induced by Flashing Instability Using the ASYST System Analysis Code

Taiyang Zhang (Univ. Illinois, Urbana-Champaign), Caleb S. Brooks (Univ. Illinois, Urbana-Champaign)

Validation Against a Small Break LOCA Scenario on ACME Test Facility: Summary of the ISP-51 Open Phase

Xueyan Zhang (Huazhong Univ. Science and Technology), Shiqi Wang (Huazhong Univ. Science and Technology), Cuiting Peng (Huazhong Univ. Science and Technology), Yuhang Huang (Huazhong Univ. Science and Technology), Zhipeng Luo (Huazhong Univ. Science and Technology), Lin Li (Huazhong Univ. Science and Technology), Yixuan Zhang (Huazhong Univ. Science and Technology), Chengcheng Deng (Huazhong Univ. Science and Technology), Jun Yang (Huazhong Univ. Science and Technology)

Verification of Transient Phenomena in RELAP5-3D: Part 1 Vessel Boiloff

Robert P. Martin (BWXT Advanced Technologies)

Verification of Transient Phenomena in RELAP5-3D: Part 2 Turbomachinery

Robert P. Martin (BWXT Advanced Technologies), Michael S. Bradbury (Information Systems Laboratories)

Two-Phase Transient Modeling of a Large Scale RCCS with RELAP5-3D

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

Assessment of the Choked Flow Model of RELAP5 for the Application of Inverse Quantification Methods

Jordi Freixa (Univ. Politècnica Catalunya), Víctor Martínez-Quiroga (Univ. Politècnica Catalunya), Gregory Perret (Paul Scherrer Institute)

A Methodology to Evaluate the Impact of Physical Distortions on Systems' Code Assessment

Marcos G. Ortiz (Information Systems Laboratories)

Comparative Analyses of the QUENCH Experiments L3HT and ATF-1 on High Temperature Oxidation Mechanisms Using AC²

Gregor T. Stahlberg (Ruhr-Univ. Bochum), Christoph Bratfisch (Ruhr-Univ. Bochum), Marco K. Koch (Ruhr-Univ. Bochum)

Simulation of Wall Condensation in a Large Amount of Non-Condensable Gases Condition Using the SPACE Code

Jong Hyuk Lee (KAERI), Kwi Seok Ha (KAERI), Seung Wook Lee (KAERI)

System Level Modeling of a Generic Pebble Bed High-Temperature Gas-Cooled Reactor (PB-HTGR) with SAM and Griffin

Zhiee Jhia Ooi (ANL), Ling Zou (ANL), Thanh Hua (ANL), Jun Fang (ANL), Rui Hu (ANL)

Validation of System Analysis Module Axial Mixing Model for Thermal Stratification and Mixing Application in the Upper Plenum of a Liquid Metal Reactor

Molly Ross (Purdue), Hitesh Bindra (Purdue), Ling Zou (ANL)

Experimental Investigation and Numerical Validation of Natural Convection in Molten Salt

J. Reis (TAMU), J. Seo (TAMU), Y. Hassan (TAMU)

Validation of the Thermal-Hydraulic Models in COBRA-TF Based on the NRC/PSU RBHT Benchmark

Yue Jin (Univ. Missouri), Fan-Bill Cheung (Penn State), Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Kirk Tien (U.S. Nuclear Regulatory Commission), Chris L. Hoxie (U.S. Nuclear Regulatory Commission)

Validation of VIPRE-W/MEFISTO-T Subchannel Analysis Code for Void Fraction Predictions in Modern BWR Fuel Assemblies

Jean-Marie Le Corre (Westinghouse Electric Sweden)

Uncertainty Analysis and Sensitivity Study on RBHT Blind Tests with Subchannel Code CTF

Lucia Rueda-Villegas (Tractebel ENGIE), Adrien Dethioux (Tractebel ENGIE), Christophe Schneidesch (Tractebel ENGIE), Jinzhao Zhang (Tractebel ENGIE)

Assessment and Testing of CTF for LOCA Reflood Conditions

R. Salko (ORNL), A. Wysocki (ORNL), B. Hizoum (ORNL), N. Capps (ORNL)

Application of CTF Subchannel Code for BWR Reload Licensing Analysis Support

K. Nikitin (Paul Scherrer Institute), B. Arnold (Paul Scherrer Institute), I. Clifford (Paul Scherrer Institute), H. Ferroukhi (Paul Scherrer Institute)

Uncertainty Quantitative Analysis on Sub-channel Code by MCMC Algorithm Based on Bayesian Principle

Xin He (Shanghai Jiao Tong Univ.), Meiqi Song (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.)

BWR Core Thermal-Hydraulic Uncertainty and Sensitivity Analysis with Improved Bypass Modeling Features

Devshibhai Ziyad (NCSU), Agustin Abarca (NCSU), Maria Avramova (NCSU)

Assessment of Subchannel Analysis Capability of Thermal-Hydraulic System Codes for Detailed Fuel Bundle Simulation

Yunseok Lee (Incheon Nat'l Univ.), Taewan Kim (Incheon Nat'l Univ.)

Numerical Investigation of Thermal-Hydraulic Behavior During the Reflood Phase Using COSINE Subchannel Code

Lin Chen (Shanghai Jiao Tong Univ.), Hao Zhang (Shanghai Jiao Tong Univ.), Lixin Du (Shanghai Jiao Tong Univ.), Yingran Guo (Shanghai Jiao Tong Univ.), Yanhua Yang (Shanghai Jiao Tong Univ.), Meng Zhao (Shanghai Jiao Tong Univ.), Yixuan Cheng (Shanghai Jiao Tong Univ.), Zhi Yang (Shanghai Jiao Tong Univ.)

Reflood Experimental Verification and Grid Sensitivity Analysis for COSINE Subchannel Code Based on Two-Fluid Eight Equations

Yixuan Cheng (Shanghai Jiao Tong Univ.), Lin Chen (Shanghai Jiao Tong Univ.), Hao Zhang (Shanghai Jiao Tong Univ.), Meng Zhao (Shanghai Jiao Tong Univ.), Yanhua Yang (Shanghai Jiao Tong Univ.)

Uncertainty Propagation and Sensitivity Analysis for a Better Understanding of the Flow Excursion Instability with the System Code CATHARE

A. Ghione (CEA)

Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting

Francesco D`Auria (Univ. Pisa), Fulvio Mascari (ENEA), Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Christophe Herer (IRSN), Miguel Sanchez Perea (CSN), Jinzhao Zhang (Tractebel ENGIE), Martina Adorni (OECD NEA)

Advances in the Analysis and Management of Accidents and Future Challenges: The OECD/NEA WGAMA

Hideo Nakamura (Japan Atomic Energy Agency), Ahmed Bentaib (IRSN), Martina Adorni (OECD NEA)

Knowledge Representation to Support EMDAP Implementation in Advanced Reactor Licensing Applications

Paridhi Athe (NCSU), Nam Dinh (NCSU), Abhinav Gupta (NCSU)

FFTBM Assessment of Reverse Natural Circulation Transient in PKL Test Facility

Q. Cai (Xi’an Jiaotong Univ.), F. D'Auria (Univ. Pisa), K. Umminger (Consultant), J. Shan (Xi’an Jiaotong Univ.)

Propagation of Uncertainties Based on Statistical Methodology for the Loss of Flow WithOut Scram Transient of the Fast Flux Test Facility

Simon Li (CEA), Georis Billo (CEA), Amandine Marrel (CEA)

Uncertainty Quantification of Deep Neural Network Predictions for Time-Dependent Responses with Functional PCA

Mahmoud Yaseen (NCSU), Ziyu Xie (NCSU), Xu Wu (NCSU)

Application of SAPIUM Guidelines to Input Uncertainty Quantification: The ATRIUM Project

A. Ghione (CEA), L. Sargentini (CEA), G. Damblin (CEA), P. Fillion (CEA), J. Baccou (IRSN), R. Sueur (EDF R&D), B. Iooss (EDF R&D), A. Petruzzi (NINE), K. Zeng (NINE), J. Zhang (Tractebel ENGIE), R. Mendizábal (CSN), T. Skorek (GRS), X. Wu (NCSU), J. Freixa (Univ. Politècnica Catalunya), M. Adorni (OECD NEA)

Neural Networks and Functional Alignment Based Bayesian Inverse UQ Using FEBA Reflood Experiment Data

Ziyu Xie (NCSU), Xu Wu (NCSU)

Uncertainty Analysis in the OECD/NEA Rod Bundle Heat Transfer Project

Kaiyue Zeng (NINE), Marco Cherubini (NINE), Alessandro Petruzzi (NINE), Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Jinzhao Zhang (Tractebel ENGIE), Martina Adorni (OECD NEA)

State of the Art for Thermal-Hydraulic Analysis of Pressurised Thermal Shock Scenarios

Ivor Clifford (Paul Scherrer Institute), Pavel Kral (Nuclear Research Institute Rez), Ladislav Vyskocil (Nuclear Research Institute Rez), Vladislav Pistora (Nuclear Research Institute Rez), Richard Trewin (Framatome), Yuliia Filonova (IPP-CENTRE), Vladislav Filonov (IPP-CENTRE), Lukasz Sokolowski (Kiwa Technical Consulting), Jürgen Hartung (GRS), Szabolcs Szávai (Bay Zoltán Foundation for Applied Research), Andrej Prošek (Jožef Stefan Institute), Jerome Roy (IRSN), Markku Puustinen (LUT Univ.), Maksym Vyshemirskyi (State Scientific and Technical Center for Nuclear and Radiation Safety), Richard Bass (Oakridge Consulting Int'l), Paul Williams (Oakridge Consulting Int'l), Takeshi Takeda (Japan Atomic Energy Agency), Carlos Cueto-Felgueroso (Tecnatom)

Evaluation of Uncertainties in Thermal-Hydraulic Analyses of PTS for the APAL European Project

Richard Trewin (Framatome), Andrej Prošek (Jožef Stefan Institute), Pavel Kral (Nuclear Research Institute Rez), Ivor Clifford (Paul Scherrer Institute), Gregory Perret (Paul Scherrer Institute), Jürgen Hartung (GRS), Inés Mateos Canals (GRS), Jerome Roy (IRSN), Vladislav Filonov (IPP-Centre), Yuliia Filonova (IPP-Centre)

BWRX-300 Chimney Evaluations (1): Conceptual Design of the Chimney

Charles Heck (Global Nuclear Fuel), Scott Bowman (Global Nuclear Fuel), Kazuaki Kito (Hitachi-GE Nuclear Energy)

BWRX-300 SMR Chimney Evaluations (2): Strategy for Qualifying TRACG Evaluations of Chimney Void Fractions

A. Povolny (Hitachi-GE Nuclear Energy), K. Katono (Hitachi-GE Nuclear Energy), C. Heck (Global Nuclear Fuel), Z. Zhang (GE Hitachi Nuclear Energy)

BWRX-300 SMR Chimney Evaluations (3): HUSTLE Testing in Large Diameter Chimney at Nominal Pressure and Temperature

Kenichi Katono (Hitachi-GE Nuclear Energy), Antonin Povolny (Hitachi-GE Nuclear Energy), Hajime Furuichi (Hitachi-GE Nuclear Energy), Kiyoshi Fujimoto (Hitachi-GE Nuclear Energy), Kenichi Yasuda (Hitachi-GE Nuclear Energy), Kazuaki Kito (Hitachi-GE Nuclear Energy)

BWRX-300 SMR Chimney Evaluations (4): Measurement of Void Fraction and Velocity Distributions in Large Diameter Chimney at Nominal Pressure and Temperature Using Double-Plane Wire-Mesh Sensor

Hajime Furuichi (Hitachi-GE Nuclear Energy), Antonin Povolny (Hitachi-GE Nuclear Energy), Kenichi Katono (Hitachi-GE Nuclear Energy), Kenichi Yasuda (Hitachi-GE Nuclear Energy), Kazuaki Kito (Hitachi-GE Nuclear Energy)

Feasibility Analysis of Flooding Safety System of i-SMR with MELCOR Code

Chang Hyun Song (Hanyang Univ.), Jae Hyung Park (Hanyang Univ.), Sung Joong Kim (Hanyang Univ.)

Boron Dilution Analysis in NuScale Using TRACE and TRACE/SCF Codes

J. Sanchez-Torrijos (Univ. Politécnica de Madrid), C. Queral (Univ. Politécnica de Madrid)

Modeling of an Overcooling Transient Scenario in a CAREM-like Small Modular Reactor

L. Mercatali (Karlsruhe Institute for Technology), V.H. Sanchez-Espinoza (Karlsruhe Institute for Technology), Hector Lestani (Comisión Nacional de Energía Atómica), Maximiliano Dalinger (Comisión Nacional de Energía Atómica)

Steam Line Break Analysis in NuScale SMR with the Coupled System Code ATHLET-DYN3D in the Framework of the EU H2020 McSAFER

Eduard Diaz-Pescador (Helmholtz-Zentrum Dresden-Rossendorf), Matthias Jobst (Helmholtz-Zentrum Dresden-Rossendorf), Alexander Grahn (Helmholtz-Zentrum Dresden-Rossendorf), Sören Kliem (Helmholtz-Zentrum Dresden-Rossendorf)

Sensitivity Study of Compact and Long-Term-Operable Passive Residual Heat Removal System

Wooseong Park (KAIST), Yong Hoon Jeong (KAIST), Yong Hwan Yoo (KAERI), Kyung Jun Kang (KAERI)

Prioritization of Regulatory Review Focuses on the Safety Analysis of Passive Safety System by REPAS Method

Ju Yeop Park (Korea Institute of Nuclear Safety), Seong-Su Jeon (FNC Technology Co.), Yougjae Park (FNC Technology Co.), Jehee Lee (FNC Technology Co.)

NRC's Methodology to Estimate Fuel Dispersal During a Large Break Loss of Coolant Accident

Andrew Bielen (U.S. Nuclear Regulatory Commission), James Corson (U.S. Nuclear Regulatory Commission), Joseph Staudenmeier (U.S. Nuclear Regulatory Commission)

Methodology and Analysis to Demonstrate Avoidance of Dispersal During a LOCA in Ringhals PWRs

J. Holmström (Ringhals), M. Holmgren (Ringhals), M. Söderström (Vattenfall Nuclear Fuel), P. Gabrielsson (Vattenfall Nuclear Fuel), A. Surén (Vattenfall Nuclear Fuel)

Reactivity-Initiated Accident Analysis of a High Burnup PWR with a 24-Month Fuel Cycle

Mason Fox (Univ. Tennessee, Knoxville), Nicholas Brown (Univ. Tennessee, Knoxville), Jianwei Hu (ORNL), Ugur Mertyurek (ORNL)

Evaluation of High-Burnup Fuel Coolability During a Control Rod Withdrawal

Isabelle Lindsay (Univ. Tennessee, Knoxville), Mason Fox (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville), Nathan Capps (ORNL)

CIFF: Analysis Model of Fuel Failure Risks Caused by CRUD Deposition

Shiwei Wang (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Hui He (Shanghai Jiao Tong Univ.)

Analysis of CRDM Nozzle Rupture LOCA with Loss of Safety Injection at the ATLAS Experimental Facility Using the MARS-KS and TRACE Code

Hyunjoon Jeong (Incheon Nat'l Univ.), Taewan Kim (Incheon Nat'l Univ.)

Good Practices for Analyses of Design Extension Condition Without Significant Fuel Degradation for Operating Nuclear Power Plants

J. Zhang (Tractebel ENGIE), M. Havet (Tractebel ENGIE), A. Bousbia Salah (Bel V), P. Kral (UJV Rez), J. Krhounkova (UJV Rez), A. Guba (Centre for Energy Research), A. Bersano (ENEA), M. Cherubini (NINE), T. Nemec (SNSA), M. Sánchez (CSN), R. Mendizábal (CSN), M. Adorni (OECD NEA), M. Bales (OECD NEA)

Sensitivity Analysis of Transient Critical Heat Flux Phenomena Within RELAP5-3D in the Transient Reactor Test Loop

Nicholas A. Meehan (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville)

Comparative Analysis of Passive Safety Feature of G-III+ BWR and PWR

Xueyan Zhang (Huazhong Univ. Science and Technology), Ye Yang (Huazhong Univ. Science and Technology), Jun Yang (Huazhong Univ. Science and Technology)

Feasibility Analysis Study of the DISNY Facility as a Test Bed for CRUD-Related Experiment Under Pressurized Water Reactor Operating Condition

Ji Yong Kim (Ulsan Nat'l Institute Science and Technology), Yunju Lee (Ulsan Nat'l Institute Science and Technology), Ju Hun Jung (Ulsan Nat'l Institute Science and Technology), Ji Hyun Kim (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)

Instability at the Interface Between Hot/Cold Fluids in the Density Lock Using Numerical Analysis for Inherently Safe Reactor

Ju Hun Jung (Ulsan Nat'l Institute Science and Technology), Ji Yong Kim (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)

A Comparison of Experimental Density Wave Instability Behavior with Analytical Model Prediction

P. Hurley (Virginia Tech), J.P. Duarte (Univ. Wisconsin, Madison)

An Improved Algorithm of Data Reconciliation for Heat Exchange System of Nuclear Power Plant Based on Bilinear Orthogonal Transformation

Tianyang Xing (Southeast Univ.), Mudi Jiang (Southeast Univ.), Xiaoliang Zhu (Southeast Univ.), Jianqun Xu (Southeast Univ.), Junling Huang (Southeast Univ.), Bin Han (Southeast Univ.), Shenhui Liu (Southeast Univ.)