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October 31–November 4, 2027
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December 2024
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Latest News
Idaho’s IWTU surpasses tank waste treatment goal
As of last week, crews with Department of Energy cleanup contractor Idaho Environmental Coalition (IEC) processed more than 142,000 gallons of radioactive sodium-bearing tank waste at Idaho’s Integrated Waste Treatment Unit (IWTU) this year.
Full Issue
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Page 0
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 22-36
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 38-55
Recent Progress in Boiling Flow Simulation Using Interface Tracking Method
Y. Sato (Paul Scherrer Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 57-70
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 96-109
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 110-122
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 123-134
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 135-143
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 146-156
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 157-167
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 168-181
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 182-195
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 196-209
Impact of Population Balance Model on Subcooled Flow Boiling Simulation
Daniel Vlček (Czech Technical Univ.), Yohei Sato (Paul Scherrer Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 212-224
Building a Boiling-Flow Multiphase CFD Framework for Nuclear Reactor Conditions
Corentin Reiss (CEA), Antoine Gerschenfeld (CEA), Catherine Colin (IMFT)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 225-238
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 239-252
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 253-266
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 268-281
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 282-295
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 296-309
Recent RELAP5-3D Developments for Water and Gas-Cooled Reactors
George L. Mesina (INL), Robert P. Martin (BWX Technologies)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 310-323
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 324-337
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 340-351
LES and RANS Modeling of an 84-pin Hexagonal Rod Bundle with Spacer Grid
Adam R. Kraus (Penn State), Elia Merzari (Penn State)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 352-365
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 366-378
Coupled RANS Simulation of Sodium-Cooled Fast Reactor Components Using the Spectral Element Code Nek5000
Nadish Saini (ANL), Haomin Yuan (ANL), Dillon Shaver (ANL)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 379-392
Large Eddy Simulation of a 61-Pin Wire-Wrapped Bundle with a Localized Blockage
Octavio Bovati (TAMU), Yassin A. Hassan (TAMU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 393-405
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 408-421
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 422-436
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 437-450
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 451-461
Development of Solids Transport Model for Fuel Dispersal Studies
Avinash Moharana (Rensselaer Polytechnic Institute), Shanbin Shi (Rensselaer Polytechnic Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 462-475
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 478-491
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 492-503
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 504-517
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 518-529
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 532-545
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 546-558
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 559-571
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 572-585
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 586-603
CFD Simulations of the UPTF-TRAM Test C1
E. Fogliatto (Paul Scherrer Institute), I. Clifford (Paul Scherrer Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 606-617
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 618-631
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 632-644
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 645-658
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 660-669
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 670-681
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 682-692
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 693-706
CFD Simulations of a LOCA Scenario for a Containment Building
Stephane Mimouni (EDF R&D), Ayouba Fofana (EDF R&D)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 707-720
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 722-735
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 736-749
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 750-763
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 764-778
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 779-792
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 794-807
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 808-821
Parametric Analysis of Flame Acceleration and Quenching Simulation with flameFoam
M. Povilaitis (Lithuania Energy Institute), J. Venckus (Lithuanian Energy Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 822-831
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 832-845
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 848-860
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 861-873
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 874-885
Flow Regime Scaling Study Aided by CFD for Large Diameter High Void Fraction Systems
Brandon Aranda (MIT), Koroush Shirvan (MIT), Emilio Baglietto (MIT)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 886-899
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 902-915
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 916-929
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 930-943
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 946-959
Pin-Wise Fuel Behavior of Nuclear Reactor Using Multi-Scale and Multi-Physics Methodology
Jae Ryong Lee (KAERI), Han Young Yoon (KAERI)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 960-971
Scaled Experiment Design for Transient Coupled CFD-Reactor Physics Model for HENRI
A. Warren (Oregon State), G. Mignot (Oregon State), W. Marcum (Oregon State)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 972-984
Numerical Simulation of Vibrating Rods in a Cross Flow in the Frame of an OECD Benchmark
Jan-Patrice Simoneau (EDF)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 985-998
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 999-1010
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1012-1022
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1023-1036
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1037-1053
Simulation of Mixed Convection Heat Transfer to Liquid Metals in Vertical Channels and Pipes
Milorad B. Dzodzo (Westinghouse Electric Co.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1054-1064
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1066-1075
Lateral Turbulent Mixing in Narrow Rectangular Channels
Basar Ozar (ANL), Jeremy R. Licht (ANL), Francesc Puig (ANL), Mohammad Kalimullah (ANL), Aurelien Bergeron (ANL)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1078-1091
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1092-1104
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1105-1120
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1121-1134
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1136-1149
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1150-1163
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1164-1177
Unipolar Charge Injection Induced Melting Rate Enhancement in a Cylindrical Thermal Energy Storage Unit
R. Deepak Selvakumar (Khalifa Univ.), Ahmed K. Alkaabi (Khalifa Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1178-1191
Quantifying HFIR Turbulence by Variable Curvature Channels
Nicholas J. Mecham (NCSU), Igor A. Bolotnov (NCSU), Emilian L. Popov (ORNL)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1194-1205
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1206-1218
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1219-1232
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1233-1246
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1248-1261
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1262-1275
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1276-1289
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1290-1301
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1304-1317
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1318-1331
On the Impact of Prandtl Number on Temperature in Parallel Jet Mixing
John Acierno (Penn State), Elia Merzari (Penn State)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1332-1345
CFD Modeling of Gas-Liquid Vertical Up-Ward Annular Flow with Thin Liquid Film
Anadi Mondal (Univ. Massachusetts, Lowell), Subash Sharma (Univ. Massachusetts, Lowell)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1346-1358
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1359-1371
Multiscale Approach for Boiling Flow Simulation
Wei Ding (HZDR), Jinming Zhang (HZDR), Hamed Setoodeh (HZDR), Dirk Lucas (HZDR), Uwe Hampel (HZDR/TU Dresden)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1374-1381
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1382-1393
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1394-1406
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1407-1420
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1426-1436
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1437-1450
RGB Mapping: A Dynamic Approach for Flow Pattern Identification and Classification
David Kang (Purdue), Drew Ryan (Purdue), Seungjin Kim (Purdue)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1451-1460
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1462-1475
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1476-1487
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1488-1499
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1502-1515
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1516-1529
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1530-1542
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1544-1554
Experimental Investigation of Heat Pipe Flow Dynamics and Performance
Ilyas Yilgor (Rensselaer Polytechnic Institute), Shanbin Shi (Rensselaer Polytechnic Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1555-1568
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1569-1581
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1582-1592
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1594-1600
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1601-1610
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1611-1619
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1620-1634
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1636-1648
Experimental PIV Measurements in a Randomly Packed Non-Isothermal Pebble Bed Core Prototype
Abdulaziz Almathami (TAMU), Blake R. Maher (TAMU), Yassin A. Hassan (TAMU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1649-1659
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1662-1675
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1676-1686
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1687-1697
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1698-1713
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1716-1726
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1727-1737
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1738-1751
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1752-1762
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1763-1776
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1778-1791
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1792-1803
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1804-1817
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1820-1833
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1834-1847
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1848-1861
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1864-1877
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1878-1891
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1892-1907
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1910-1923
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1924-1934
Spray Cooling of a Rod Bundle with a Counter-Current Steam Flow in Spent Fuel Pool Conditions
G. Brillant (IRSN)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1935-1945
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1946-1956
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1958-1971
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1972-1984
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1985-1998
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 1999-2011
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2014-2025
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2026-2039
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2040-2050
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2051-2061
Experimental Investigations of Material-Conjugated Subcooled Flow Boiling
Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2064-2087
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2088-2101
Steady-State and Power Transient Critical Heat Flux Experiments of FeCrAl and Zircaloy Claddings Under Saturated Pool Boiling
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2102-2115
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2116-2125
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2128-2139
Flow Rate Measurement Across the Upper Core Structure of a Sodium Fast Reactor
D. Guenadou (CEA), P. Aubert (CEA), J-P Descamps (CEA)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2140-2151
High-Resolution Experiments for Mixing in Large Enclosures
J. Mao (Univ. Michigan), V. Petrov (Univ. Michigan), A. Manera (ETH Zürich)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2152-2165
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2166-2179
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2182-2195
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2196-2209
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2210-2222
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2223-2232
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2234-2247
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2248-2255
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2256-2269
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2270-2281
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2282-2293
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2296-2309
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2310-2320
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2321-2334
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2335-2346
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2348-2361
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2362-2375
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2376-2386
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2388-2401
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2402-2415
RIVA: A New Experimental Facility for Fast Blowdown and Pressurization of Small Containment
Lucia Sargentini (CEA), Constantin Ledier (CEA), Arnaud Chazottes (CEA)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2416-2429
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2430-2443
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2448-2461
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2462-2474
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2475-2486
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2487-2503
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations
Drew Ryan (Purdue), Seungjin Kim (Purdue)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2504-2517
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2520-2533
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2534-2548
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2549-2560
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2561-2573
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2574-2581
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2584-2597
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2598-2606
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2607-2620
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2621-2628
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2630-2643
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2644-2653
Critical Heat Flux Dependence on Liquid Height in Subcooled Pool Boiling
Rodrigo Cavalcanti Alvarez (MIT), Matteo Bucci (MIT)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2654-2665
Predictions of Westinghouse TRITON11 BWR Fuel Critical Power Performances with MEFISTO-T Subchannel Analysis Code
Jean-Marie Le Corre (Westinghouse Electric Sweden)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2668-2681
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2682-2691
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2692-2701
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2704-2717
Enhancing Nanoscale Heat Pipe with Hydrophilic/hydrophobic Pattern: A Molecular Dynamics Study
Wei Deng (City Univ. Hong Kong), Jiyun Zhao (City Univ. Hong Kong)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2718-2731
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2732-2742
AC2-ATHLET Simulations of PERSEO Test Facility
Sebastian Buchholz (GRS)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2743-2753
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2754-2762
The Effect of Data Split on Correlation Errors with Respect to Independent Validation Data
Kanghoon Kim (KEPCO Nuclear Fuel), Boemjun Jang (KEPCO Nuclear Fuel)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2764-2771
Investigation of the DNBR Criteria Application for NPP Safety Studies
Attila Guba (Centre for Energy Research), Áron Hegedüs (Centre for Energy Research)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2772-2784
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2785-2798
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2799-2808
Low Pressure Low Flow Rod Bundle CHF and its Challenges in SMR
Bao-Wen Yang (DEQD), Bin Han (Southeast Univ.), Aiguo Liu (DEQD)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2809-2818
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2820-2833
Scaling Effects in Intermediate Break LOCA Scenarios
Kevin Martin (UPC), Jordi Freixa (UPC), Victor Martinez-Quiroga (UPC)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2834-2847
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2848-2864
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2865-2878
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2879-2885
Natural Convection Heat Transfer with Molten Salt in a Differentially-Heated Cavity
Noah LeFrancois (McGill Univ.), Jovan Nedic (McGill Univ.), Melanie Tetreault-Friend (Hatch)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2888-2896
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2897-2910
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2911-2924
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2925-2936
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2942-2943
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2943-2943
3D Imaging of Phase Structures Using Fibre Bragg Grating Grid Sensors
Harvey Oliver Plows (Bangor Univ.), Marat Margulis (Bangor Univ.), Jinfeng Li (Bangor Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2944-2944
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2945-2945
COMSOL Multiphysics Modeling Results for the Low Enriched Uranium-Silicide Conversion of the High Flux Isotope Reactor
Prashant K. Jain (ORNL)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2946-2946
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2947-2947
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2948-2959
Large Eddy Simulation of Thermal Mixing of Liquid Sodium in a T-Junction
Xiaoxue Huang (Univ. Sheffield), Shuisheng He (Univ. Sheffield)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2949-2949
Measurements of Near-Wall Turbulence in Water by Molecular Tagging Velocimetry
Charles Fort (George Washington Univ.), Philippe Bardet (George Washington Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2950-2950
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2951-2951
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2954-2954
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2955-2955
Embedded Borescopic Molecular Tagging Velocimetry Within PWR Surrogate Bundle
Roberto Capanna (George Washington Univ.), Philippe M. Bardet (George Washington Univ.), Guillaume Ricciardi (CEA)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2956-2956
Simultaneous High-Speed Flow Velocimetry and Pressure Measurements in Water Hammer
Roberto Capanna (George Washington Univ.), Philippe M. Bardet (George Washington Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2957-2957
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2958-2958
Modeling of Triggering and Steam Explosion Pressure Propagation with Validation Against KROTOS Experiments
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2959-2959
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2960-2960
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2961-2961
The Effect of Aerosol Particle Density on Aerosol Release Potential in LMR Source Term Experiments
John C. Petrykowski (Vibration Heat Flow and Analysis)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2962-2962
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2966-2979
Experimental Research of the MYRRHA Primary Pump Hydraulic Characteristics at a Reduced Scale
Mikhail Iarmonov (SCK CEN), Katrien V. Tichelen (SCK CEN)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2980-2985
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 2986-2999
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3000-3013
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3014-3027
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3030-3043
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3044-3057
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3058-3071
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3072-3082
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3084-3097
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3098-3114
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3115-3125
Optimization of the Emergency Coolant Injection System of ALLEGRO
Boris Kvizda (VUJE), Slavomír Bebjak (VUJE)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3126-3139
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3140-3154
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3156-3169
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3170-3183
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3184-3193
Flow-Informed Corrosion in Molten Salts Using the Poisson-Nernst-Planck Model
M. Tano (INL), S. Walker (INL), A. Abou-Jaoude (INL)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3194-3207
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3208-3221
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3224-3237
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3238-3251
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3252-3260
Turbulence Characteristics Using Dynamic Mode Decomposition in an 84-Pin Hexagonal Fuel Assembly
Craig Menezes (TAMU), Yassin A. Hassan (TAMU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3261-3274
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3276-3289
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3290-3304
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3305-3318
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3319-3331
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3332-3344
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3346-3359
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3360-3373
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3374-3387
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3388-3400
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3401-3414
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3416-3427
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3428-3439
The Effects of Depressurizing into a Cavity for Small and Medium Sized Break Air Ingress Accident Scenarios
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3440-3453
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3456-3467
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3468-3478
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3479-3492
Nuclear Spaceship for Interplanetary Cruise Using a Micro Fast Reactor
Tadashi Narabayashi (Tokyo Institute of Technology)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3493-3506
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3507-3520
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3522-3534
lbh15: A Python Package Implementing Lead, Bismuth, and Lead-Bismuth Eutectic Thermophysical Properties for Fast Reactor Applications
Daniele Panico (newcleo), Daniele Tomatis (newcleo)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3535-3546
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3547-3559
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3560-3570
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3572-3585
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3586-3598
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3599-3612
CFD Thermal Analysis of eVinci™ Microreactor -- Integrating Reactor Core and Primary Heat Exchanger
Hong Xu (Westinghouse Electric Co.), Liping Cao (Westinghouse Electric Co.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3613-3622
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3623-3636
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3638-3651
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3652-3662
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3663-3676
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3677-3688
Passive Temperature-Sensitive Flow-Controlling Device Based on Bimetallic Membrane Deflection, FEM, and CFD Feasibility Study
Victor Petrov (Univ. Michigan), Yucan Ding (Univ. Michigan)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3690-3700
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3701-3712
Heat Pipe Cooling System Reliability Analysis with Cascading Effect
Gyun Seob Song (Chung-Ang Univ.), Man Cheol Kim (Chung-Ang Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3713-3720
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3721-3727
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3732-3745
Investigation of Starting Time Characteristics of Source Term Release for Dissimilar Nuclear Accident Consequence
Wasin Vechgama (KAERI), Jaehyun Cho (Chung-Ang Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3746-3758
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3759-3771
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3774-3784
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3785-3794
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3795-3808
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3810-3823
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3824-3837
Investigation of Reynolds Stress Models for RANS of Natural Convection of a Corium Pool for in-Vessel Retention
D. Dovizio (Nuclear Research & Consultancy Group)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3838-3850
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3851-3862
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3864-3877
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3880-3891
Analysis of Corium Coolability in MCCI Conditions for Two Types of Concrete, Using ASTEC Calculations
C. Bouillet (IRSN)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3892-3905
Simplified Model for One-Dimensional Ex-Vessel Corium Coolability
Jaehoon Jung (KAERI), Seokgyu Jeong (KAERI)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3906-3916
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3917-3930
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3932-3944
The Role of Zr-Oxidation During Molten Core-Concrete Interaction
Xiaoyang Gaus-Liu (Karlsruhe Institute of Technology)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3945-3955
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3956-3969
Steam Explosion Retardant for Long-Term Coolability
Masahiro Furuya (Waseda Univ.), Takahiro Arai (CRIEPI)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3970-3977
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3978-3992
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 3994-4005
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4006-4019
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4020-4033
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4034-4044
Influence of Iodine Chemistry in I2 Scrubbing Modeling
Adolf Rydl (INSET), Taizo Kanai (Central Research Institute of Electric Power Industry)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4046-4058
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4059-4072
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4073-4085
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4086-4099
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4102-4113
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4114-4123
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4124-4136
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4137-4150
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4152-4164
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4165-4178
A Numerical Study for Modeling Sprays in TOSQAN-101 Experiment Using OpenFOAM
Keun Sang Choi (KAERI), Jaehoon Jung (KAERI), Gun-Hong Kim (OpenCAE)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4179-4189
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4190-4203
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4206-4219
The iPWR MELCOR 2.2 Parametric Sensitivity Analysis
Mateusz Malicki (Paul Scherrer Institute), Piotr Darnowski (Warsaw Univ. Technology), Terttaliisa Lind (Paul Scherrer Institute)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4220-4233
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4234-4247
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4248-4255
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4256-4266
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4268-4280
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4281-4294
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4295-4308
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4310-4321
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4322-4335
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4336-4349
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4350-4363
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4364-4379
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4384-4396
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4397-4410
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4411-4424
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4425-4433
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4436-4449
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4450-4463
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4464-4475
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4476-4488
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4489-4502
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4504-4515
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4516-4529
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4530-4543
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4544-4557
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4560-4573
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4574-4587
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4588-4601
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4602-4615
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4618-4631
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4632-4645
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4646-4658
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4659-4672
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4674-4687
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4688-4701
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4702-4715
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4716-4729
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4732-4744
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4745-4760
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4761-4770
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4771-4780
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4782-4795
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4796-4809
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4810-4822
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4823-4836
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4838-4850
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4851-4864
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4865-4879
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4880-4893
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4896-4905
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4906-4917
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4920-4933
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4934-4947
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4948-4961
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4962-4975
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4978-4990
Deep Generative Modeling for Augmentation of the Steady-State Void Fraction Dataset in the BFBT Benchmark
Farah Alsafadi (NCSU), Xu Wu (NCSU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 4991-5003
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5004-5017
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5018-5032
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5034-5047
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5048-5057
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5058-5071
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5072-5082
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5084-5094
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5095-5107
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5108-5121
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5122-5135
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5136-5145
Flow Regime Classification Using Orientation-Independent Layered Spectral Clustering
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5148-5159
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5160-5173
Application of Structure-Based Machine Learning Model on Thermal Striping Evaluation
Yu-Jou Wang (MIT), Emilio Baglietto (MIT), Koroush Shirvan (MIT)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5174-5187
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5188-5201
A Platform for a Machine Learning Diagnosis of the Severe Accident
JinHo Song (Hanyang Univ.), SungJung Kim (Hanyang Univ.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5204-5217
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5218-5226
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5228-5241
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5242-5252
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5253-5266
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5267-5280
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5282-5294
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5295-5308
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5309-5319
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5320-5333
Validation on SBLOCA Experiment of the ACME Test Facility Using the ATHLET Code
Liancheng Guo (GRS), Thorsten Hollands (GRS), Henrique Austregesilo (GRS)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5338-5347
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5348-5357
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5358-5370
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5371-5382
Verification of Transient Phenomena in RELAP5-3D: Part 1 Vessel Boiloff
Robert P. Martin (BWXT Advanced Technologies)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5384-5397
Verification of Transient Phenomena in RELAP5-3D: Part 2 Turbomachinery
Robert P. Martin (BWXT Advanced Technologies), Michael S. Bradbury (Information Systems Laboratories)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5398-5411
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5412-5425
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5426-5439
A Methodology to Evaluate the Impact of Physical Distortions on Systems' Code Assessment
Marcos G. Ortiz (Information Systems Laboratories)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5440-5447
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5450-5461
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5462-5473
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5474-5486
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5487-5498
Experimental Investigation and Numerical Validation of Natural Convection in Molten Salt
J. Reis (TAMU), J. Seo (TAMU), Y. Hassan (TAMU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5499-5510
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5512-5525
Validation of VIPRE-W/MEFISTO-T Subchannel Analysis Code for Void Fraction Predictions in Modern BWR Fuel Assemblies
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5526-5540
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5541-5554
Assessment and Testing of CTF for LOCA Reflood Conditions
R. Salko (ORNL), A. Wysocki (ORNL), B. Hizoum (ORNL), N. Capps (ORNL)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5555-5568
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5569-5578
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5580-5593
BWR Core Thermal-Hydraulic Uncertainty and Sensitivity Analysis with Improved Bypass Modeling Features
Devshibhai Ziyad (NCSU), Agustin Abarca (NCSU), Maria Avramova (NCSU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5594-5607
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5608-5615
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5616-5627
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5628-5639
Uncertainty Propagation and Sensitivity Analysis for a Better Understanding of the Flow Excursion Instability with the System Code CATHARE
A. Ghione (CEA)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5642-5653
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5654-5667
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5668-5678
Knowledge Representation to Support EMDAP Implementation in Advanced Reactor Licensing Applications
Paridhi Athe (NCSU), Nam Dinh (NCSU), Abhinav Gupta (NCSU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5679-5692
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5693-5703
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5706-5719
Uncertainty Quantification of Deep Neural Network Predictions for Time-Dependent Responses with Functional PCA
Mahmoud Yaseen (NCSU), Ziyu Xie (NCSU), Xu Wu (NCSU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5720-5733
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5734-5747
Neural Networks and Functional Alignment Based Bayesian Inverse UQ Using FEBA Reflood Experiment Data
Ziyu Xie (NCSU), Xu Wu (NCSU)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5750-5763
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5764-5777
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5778-5790
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5791-5805
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5810-5823
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5824-5837
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5838-5846
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5847-5860
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5861-5870
Boron Dilution Analysis in NuScale Using TRACE and TRACE/SCF Codes
J. Sanchez-Torrijos (Univ. Politécnica de Madrid), C. Queral (Univ. Politécnica de Madrid)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5872-5881
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5882-5894
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5895-5908
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5909-5921
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5924-5936
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5938-5951
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5952-5963
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5964-5977
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5978-5990
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 5991-6004
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6006-6019
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6020-6033
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6034-6047
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6048-6061
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6064-6076
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)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6077-6089
A Comparison of Experimental Density Wave Instability Behavior with Analytical Model Prediction
P. Hurley (Virginia Tech), J.P. Duarte (Univ. Wisconsin, Madison)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6090-6100
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.)
Proceedings | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) | Washington, D.C., August 20-25, 2023 | Pages 6101-6114