2024: 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety | Proceedings of the Canadian Nuclear Society

K.I. Ahn, D. Luxat, Fabrizio Gabrielli, Fulvio Mascari, V. Martinez-Quiroga, R. Pericas, B. Khuwaileh, Y.J. Cho, X. Cao, B. Foad, S. Ali, Federico Mezio, T. Jevremovic

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Void Redistribution Measurement Downstream of Part-length Rods in Rod Bundle with High-Energy X-Ray CT

Taku Arai, A. Ui, M. Furuya, R. Okawa, T. Iiyama, S. Ueda, K. Shirakawa

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Assessment of Two-Phase Flow Predictability of 3D Components in MARS-KS and TRACE in Rod Bundle Geometry

Yun Seok Lee, Taewan Kim

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Development of an Advanced Freeze Valve System for Molten Salt Reactor

Chan Lee, Dongyeol Yeo, Yun Bum Park, Gyeong-Hoi Koo, Hyuong Suk Yu, Sooseong Park, Yong Hoon Jeong

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Modeling of Heterogeneous Nucleation from Surface Nuclei and Application to the Evaluation of the Void Ratio in a Molten Salt Reactor

Nicolas Guéritat, Serge Maillard, Jacques Léchelle, Pablo Rubiolo, Veronique Ghetta

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MELCOR Model of iPWR and Application to Emergency Planning Zone Study

John Cui, Luke Lebel, Andrew C. Morreale, David W. Hummel

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Evaluation and Demonstration of Predictive Capability Maturity Quantification (PCMQ) Method for Assessing Software Validation and Applicability

J.W. Lane, P. Gorman, A. Alfandi, T.M. Moore, M. Nudi

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Experimentation and Modeling of Subcooled Flow Boiling from the Perspective of Large Bubble Formation

Tomio Okawa, Thanh-Binh Nguyen, Ryoma Tsujimura

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Conceptual Design of Component Test Facility (CTF) for Investigation of FACE Phenomenon in Molten Lead

Sumathi Vasudevan, Ignas Mickus, Kin Wing Wong, Dmitry Grischenhko, Pavel Kudinov

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Analyses of an Integral Pressurized Water Reactor During Postulated Accident Conditions Using the System Code Package AC²

Gregor T. Stahlberg, Julia Krieger, Marco K. Koch

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Development of Thermalhydraulic Modelling and Simulation Capabilities in CNL in Support of Advanced Reactors

Krishna Podila, Qi Chen, Peter Pfeiffer, Aleksandar Vasić, Nusret Aydemir, Xianmin Huang, Geoff Waddington

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Thermal-Hydraulic Behavior in Containment as Influenced by Steam Injection Location: Insights from the OECD-ATLAS3 C5.2 Separate Effect Tests

Jae Bong Lee, Byoung-Uhn Bae, Yusun Park, Kyoung-Ho Kang

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Preliminary Assessment of Cooling Performance in Small Modular Reactor Metal Containment Vessel according to the Filling Gas Types.

Geunyoung Byeon, Beomjin Jeong, Namgook Kim, Geon Hyeong Lee, Jin Ho Song, Sung Joong Kim

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Transient Simulation of a Steam Rankine Cycle using CATHARE-3 System Thermal-hydraulic Code: Application to Superphenix Fast Reactor

Vincent Audoly, Laura Matteo, Claire Vaglio-Gaudard, Gedeon Mauger, Nicolas Tauveron

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Robust Abnormality Diagnosis Model Considering Nuclear Power Plants Data Trends

Seung Gyo Cho, Seung Jun Lee

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Comparison Between EDF MAAP5.04 and ASTECv3 Codes on Hypothetical Severe Accidents in an Integral PWR

Jeremy Bittan, Nikolai Bakouta, Mirco Di Giuli, Ali Swaidan

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A Comprehensive Study of Aerosol Transport and Deposition Behavior in Severe Reactor Accidents: Experimental and Modeling Approaches

Md. Iqbal Hosan, Takanishi Kohei, Akihiro Kakoi, Koji Morita, Wei Liu, Xu Cheng

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A Three-Dimensional Multiphysics CFD Analysis of Cobalt Adjuster Units in CANDU Reactors – In Core Operation

Assem Elzaabalawy, Ahmed Elkholy, Mohamed Aboulella, Qasim Khan, Waleed Mekky

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A Computational Investigation on Fuel Dispersal Phenomena during Large Break Loss of Coolant Accident in LWRs

Avinash Moharana, Shanbin Shi, Kyle A. Gamble, Benjamin W. Spencer

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The Influence of Fuel Bundle Misalignment and Pressure Tube Aging on Mass Flow Rate Distribution in CANDU Fuel Channels

Ahmed Elkholy, Assem Elzaabalawy, Mohamed Aboulella, Qasim Khan, Waleed Mekky

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Analysis of IBLOCA Scenarios in ATLAS: Simulation Approaches with the TRACE Code

M. Lorduy-Alós, S. Gallardo, G. Verdú

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Testing of Reflood Heat Transfer Under Very-Low Flooding Rate Conditions at the NRC-PSU RBHT Facility

Molly K. Hanson, Brian R. Lowery, Michael P. Riley, Douglas J. Miller, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie

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Evaluation of Particle Size Distribution Models in STAR-CCM+ and OpenFOAM for Dispersed Two-Phase Flows

Brandon Aranda, Emilio Baglietto, E.M.A. Frederix

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Fukushima Daiichi Nuclear Power Plant Accident Analysis Considering the Thermal Stratification and Containment Leakage

Yuki Nakamura, Yoshihiro Kojima, Takuya Yamashita, Kenta Shimomura, Shinya Mizokami

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Novel Approach for Modeling Effective Delayed Neutron Fraction and Transient Reactivity Feedback Effects for Circulating Fuel Reactors

J.W. Lane, T.M. Moore, A. Mausolff

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Approach for Rod Burst Ratio Evaluation during Loss-Of-Coolant Accident with DRACCAR software

Sebastien Belon, Tatiana Taurines, Tony Glantz

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Severe Accident Analysis of High Pressure Sequences for APR1400 using CINEMA Computer Code

Rae-Joon Park, Jaehyun Ham, Dong Gun Son, Sang Ho Kim, Jaehoon Jung

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Coupled Thermal-Hydraulics and Neutronics Simulation using Sub-Channel CFD and SERPENT

Bryan Tan, Yu Duan, Matthew D. Eaton, Michael J. Bluck, Bo Liu

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Mechanistic Modeling of Departure from Nucleate Boiling in Subcooled Flow Boiling at Near-Critical Pressure Conditions

Laura Licht, Sebastian Leopoldus, M. Westermeier, C. Schifflechner, H. Spliethoff

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Development of a Source Terms Migration Model for CDA Bubble

Zeren Zou, Wei Liu, Koji Morita

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Comparison Analysis on Spreading Distance of Spill Molten Salt with Molten Core Material using Analytical Model

Rae-Joon Park, Jun Young Kang, Sang Mo An, Jun Ho Bae, Sung Il Kim

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Keynote: CEA Fukushima Investigations for Ex-Vessel Debris Retrieval and Decommissioning

Christophe Journeau, Viviane Bouyer, Arthur Denois, Andrea Bachrata, Laurent Brissonneau, Ioana Doyen, Celia Guevar, Emmanuelle Brackx

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Advancements in High-Temperature Measurement Techniques to Aid Development and Enhance Monitoring of Advanced Reactors

Matthew Leoschke, Christopher Balbier, Scout Bucks, Saya Lee, Federico Scurti

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Plaid-BC Algorithm for Direct Numerical Simulation of Boiling Phenomena

Nicholas J. Mecham, Igor Bolotnov

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Comprehensive Verification and Validation of 2D and 3D RANS Turbulence Models in the Mixing Region of Three Parallel Channels Across Diverse Reynolds Numbers

Evan R. Bures, Abdullah G. Weiss, Mark L. Kimber

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Measurements of Boiling Two-Phase Flow Dynamics in a Heated Tube Using Neutron Transmission Imaging

Daisuke Ito, Naoya Odaira, Kei Ito, Yasushi Saito

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Experiments on Passive Heat Removal of Fully and Partially Immersed Containments by Laminar and Turbulent Convection at Very High Rayleigh Numbers

K. Dieter, M. Freitag, B. von Laufenberg, E. Schmidt, S. Gupta

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CFD Simulation of High Temperature Corium Interaction with Coolant in Pre-flooded Cavity

J.W. Choi, I.S. Ra, G.Y. Tak, J.H. Eom, H.Y. Jeong

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Performance Study of High-temperature Latent Heat Storage for Integration with Advanced Nuclear Reactors

Jun Soo Yoo, Sunming Qin, Jeremy L. Hartvigsen, Daniel Mikkelson, Rami Saeed, Joseph Seo, Hansol Kim, Yassin A. Hassan

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The Impact of Thermal-Hydraulic Information on Nuclear Fission Product Behavior Simulation Using the SIRIUS Module in the CINEMA Code

Yongjun Lee, Chang Hyun Song, Joon Young Bae, Jin Ho Song, Sung Joong Kim

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Experimental Investigation of Heat Pipes as a Passive Cooling System for a Spent Fuel Pool: The Effects of Air Velocity and Temperature

M.S. Lee, Hyuong Suk Yu, Yong Hoon Jeong

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Comparative Analysis of Particle Retention Models in Filtered Containment Venting Systems

Miriam Muer, Marco K. Koch

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Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents

Semin Joo, Yeonha Lee, Seok Ho Song, Jeong Ik Lee

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Numerical Modelling of Two-Phase Critical Flow in a Steam Generator Guillotine Tube Rupture Scenario

Giteshkumar Patel, Lauri Pyy, Sharandeet Singh, Andrei Zaitsev, Juhani Hyvarinen

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Evaluation of Interface Capturing Schemes of VOF Method through Application to Bubble Flows with Single Orifice

Takanari Fukuda, Susumu Yamashita, Hiroyuki Yoshida

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Integral Effect Test on Intermediate Break Loss-of-coolant Accident with Coupling RCS and Containment in ATLAS-CUBE Facility

Byoung-Uhn Bae, Kyoung-Ho Kang, Jae Bong Lee, Yusun Park, Seok Cho, Jun-Yeong Jung, Kyoung-Ho Kang

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MIDI, a Facility Dedicated to Study the Thermal Hydraulic Characteristics of Spent Fuel Pools

Benoît Migot, Jimmy Martin, Emmanuel Rougé, Sandrine Morin

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Integrated Simulation of Rod Ejection Accidents in Boron-Free Pressurized Water Reactors Using S5K Neutronics and VIPRE-01 Sub-channel Solvers

Haleem Haroon, Ben Cooper, Robert Gregg

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CSNI Code Validation Matrix (CCVM) Current Status and Development Needs

Fulvio Mascari, Ahmed Bentaib, P. Ruyer, M. Adorni, Andrew C. Morreale, Thorsten Hollands, H.S. Park, P. Dejardin, H. Nakamura

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Thermal-Hydraulic Study of the Converter Facility in the FRM II Research Reactor using Serpent 2 and Ansys CFX within the Framework of the LEU Conversion Program

Kaltrina Shehu, Daniel Bonete-Wiese, Tobias Chemnitz, Christian Reiter

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Development of a Condensation Model for Realistic Analysis of Heat Removal Behavior by Passive Heat Sinks within a Containment

Jia Yu, Yeon-Gun Lee

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Comparative Study of Cold Ramp Tests Simulations with the Thermo-Mechanical Code TESPA-ROD and the Subchannel Code CTF

Yann Périn, Jonathan Sappl

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Numerical Investigation on Gas and Powder Flow Characteristics of Pebble Bed of Fusion Blanket

Jian Wang, Mingzong Liu, Mingzhun Lei

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Computational Fluid Dynamics Investigation of the Impact of 6% Crept Pressure Tubes on Flow Behavior, Fuel Temperatures, and Pressure Tube Wall Temperatures of a Single CANDU 37M Fuel Bundle

Z. Lu, M.H.A. Piro

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Potential Applications and Recommendations of Dynamic Event Tree Analysis using DICE(Dynamic Integrated Consequence Evaluation)

Gyunyoung Heo, Dohun Kwon, Yuntae Gwak, Yongjoon Lee

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Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (3) Material Analysis of Boron Carbide Immersed in Molten Stainless-Steel

Toshihide Takai, Yuki Emura, Hidemasa Yamano

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Source Term Analysis in the Fuel Degradation Phase of PHEBUS FPT-1 Experiment using MELCOR 2.2

Han Sol Park, Yeon-Gun Lee

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Preparing the MACCS Code for Advanced Reactor Applications

Mariah Garcia

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Coupled CFD-STH Modelling of the ATHENA Lead-Cooled Pool Type Facility

Roberto Zanino, Pietro Cioli Puviani, Tommaso Del Moro, Fabio Giannetti, Ivan Di Piazza, Dario Diamanti, Mariano Tarantino

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Towards CFD Modelling of the Lower Plenum Mixing Test of the OSU High Temperature Test Facility

M.M.M.D. Hussain, Ferry Roelofs

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Influence of ATF Coatings on the Critical Heat Flux in a Vertical Rod Bundle during Flow Boiling of Water at Low Pressure

Nicolas Wefers, Wilson Heiler, Stephan Gabriel, Andreas Class

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Experimental Investigation on Helium Drag Effect in Terms of Natural Circulation Enhancement for Passive Molten Salt Fast Reactor (PMFR)

Won Jun Choi, Jae Hyung Park, Seung Gyu Hyeon, Jin Ho Song, Sung Joong Kim, Sung Joong Kim

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Current Status of Cr-coated Claddings in Severe Accident Codes and Evaluation within the Frame of the QUENCH-ATF-1 Benchmark of OECD Project QUENCH-ATF

Thorsten Hollands

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Numerical Investigations of Ball Valve Performance in Variable Valve Diameters, Openings and Flow Regimes

Anutam Bairagi, Minghui Chen

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Intelligent Control System Design for Implementation of Control Strategies for Supercritical CO2 Brayton Cycle-Cooled Reactor System

Ghulam Jillani, Jianqiang Shan, Wu Pan

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Optical Fiber Temperature Sensor Performance Test in a Metallic Capillary Tube at High Temperatures

Christopher Balbier, Scout Bucks, Erik Hisahara, Saya Lee, Federico Scurti

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COAL Reflooding experiments during a Loss Of Coolant Accident : effect of the water flow rate and the residual power with ballooned rods

Georges Repetto, R.A. Fortman, R. Van Lochem

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Computational Fluid Dynamics Analysis of Phase One of the OECD‐NEA / NRC Benchmark on Liquid Metal Fast Reactor Thermal Hydraulics

D. Holler, M. Iffat Faizee, Maria Avramova

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Establishing a LOCA Fuel Safety Evaluation Methodology for Assessment of Advanced Technology Fuel Performance Using FRAPTRAN-TE-1.5

Jinzhao Zhang, Thomas Drieu

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Computational Fluid Dynamics Analysis of Phase One of the OECD‐NEA Benchmark on CANDU Thermal-Hydraulics

D. Holler, J. Geymer, Maria Avramova

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Coupled Computational Fluid Dynamics (CFD) and Finite Element (FE) Thermal Stress Analysis of Thermal Fatigue Phenomena within a T-junction

L Lampunio, Yu Duan, Matthew D. Eaton, Michael J. Bluck, M.C. Davies, A Sergis, Y Hardalupas, R. Tunstall, H. Davies

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Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (2) Modeling of Multi-Phase Eutectic Reaction Behavior

Koji Morita, Hidemasa Yamano

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Uncertainty Quantification (UQ) for the Analysis of Thermal Stresses within a T-junction Pipe Wall Using a Structured Gaussian Process (GP) Method

L Lampunio, Yu Duan, Matthew D. Eaton, Michael J. Bluck, M.C. Davies, A Sergis, Y Hardalupas, R. Tunstall, H. Davies

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Preliminary Study of Microreactor Emergency Planning Zone

Erik Hisahara, Christopher Balbier, Saya Lee, Rohan Biwalkar, Sola Talabi

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A Preliminary Severe Accident Analysis of a Generic Small Boiling Water Reactor

Feng Zhou, Andrew C. Morreale, Luke Lebel, John Cui, Garik Patterson

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Interface Resolved Simulation of Two-Phase Flow within a Steam Separator Geometry

Taylor Grubbs, M. Iffat Faizee, Igor Bolotnov

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A Summary of the Uncertainty and Sensitivity Analysis of a Generic CANDU 6 Plant by Means of Severe Accident Codes in the Framework of the IAEA CRP I31033

Sergei M. Petoukhov, Andrew C. Morreale

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Advanced Thermal Monitoring in Scaled Reactors using Deep Learning-Enhanced Drone IR Imaging

Do Yeong Lim, Ik Jae Jin, In Cheol Bang

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Numerical Study of Two-Stage Safety Injection Tank in a Small Modular Reactor

Soo Jai Shin, Young In Kim, Seungyeob Ryu, Youngmin Bae, Hyunjun Cho

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On the Influence of Model Uncertainty in Thermal Stratification Simulations of Pool-Type Sodium-Cooled Fast Reactors using Computational Fluid Dynamics

Yu-Jou Wang, Emilio Baglietto

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Data-Driven Prediction of Preheater Steady-State Conditions Based on Support Vector Regression

Xubin Wu, Wentao Hao, Wenwen Zhang, Zhenlei Liu, Weihua Li

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Nuclear Power Plant Condenser Improvement

Preston Tang, Akash Bhatia, Leon Cramer, David Zobin

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Preliminary Study on the Integration of Organic Rankine Cycle with the Low-Temperature Heating Reactor

De-en Song, Wenwen Zhang, Wentao Hao, Weihua Li, Wei Peng

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System-Level Thermal-Hydraulics Analysis of the Proposed NIST Neutron Source Design

Anil Gurgen, Abdullah G. Weiss

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Prediction of Single Channel Critical Heat Flux by Machine Learning Approaches

Yen-Hsun Wang, Yang-Cheng Shih, Cheng-Chuan Lin, Bao-Wen Yang, Jeremy Silber

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Numerical and Experimental Study of Radiative Heat Transfer with Radiation Shielding for Application of Metal Containment Vessel Design in Small Modular Reactor Development

Beomjin Jeong, Geon Hyeong Lee, Geunyoung Byeon, Namgook Kim, Sung Joong Kim

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Investigation of Thermal Limitations in Heat Pipes Using Three Different Working Fluids in a Heat Pipe Reactor

Gizem Bakir

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CFD Analysis of Hydrogen within a Filter-Vented Canister Containing Fukushima Fuel Debris

H. Shirai, T. Fujisaki, K. Enomoto, D. Fujiwara, R. Sakiyama, E. Shimizu, K. Ishikawa, H. Kobayashi

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Fuel Fragment Jamming Inside Fuel Rods Following a LOCA

Gordon J. Wissinger

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Morphology Change of CRUD Formed on Fuel Cladding by Deposition Time in Pressurized Water Reactor Environment

Yunju Lee, Junhyuk Ham, Junhyuk Jeong, Ji Hyun Kim

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An Integrated Fiber Optic and Acoustic Leak Detection Technologies for Nuclear Power Plants Water Supply and Reactor Cooling Systems

Bao-Wen Yang, Jeremy Silber

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Research on Resistance and Flow Characteristics of 7-Rod Bundles with Simple Support Grid at Reynolds Numbers of 1000-10000

Yang Liu, Qianwan Shi, Long Gu, Dajun Fan, Rongjie Li

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Experimental Investigation on Aerosol Scavenging by Electrically Charged Spray with Preinjected Water Mist for Fukushima Daiichi Decommissioning

Ruicong Xu, Avadhesh Kumar Sharma, Erdal Ozdemir, Shuichiro Miwa, Koji Okamoto, Shunichi Suzuki

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Subchannel Simulation of Rod-Bundle Two-Phase Flow Experiments with Flica5

Xavier Manchon, Théotime Le Borgne de Palfray, Ianis Cosnier

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Loss-of-Heat-Sink Transient Simulation with RELAP5/Mod3.3 Code for the ATHENA Facility

Fabio Giannetti, Tommaso Del Moro, Pietro Cioli Puviani, Ivan Di Piazza, Dario Diamanti, Mariano Tarantino

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Three-Dimensional Lagrangian-Eulerian Modeling and Analysis of Fuel-Coolant Interaction

Kwang-Hyun Bang, Kwang-Hyun Bang, Min-Soo Kim, Dong-Jin Shin, Dong-Ha Kim

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ARIANT and RELAP5-3D Simulation of OECD-NEA Benchmark Against the Oregon State University High Temperature Test Facility Data

Xianmin Huang, Tariq Jafri, Geoff Waddington

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Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages

Ferry Roelofs, Akshat Mathur, Heleen Uitslag-Doolaard, Markus Daubner, Karsten Litfin, Julio Pacio

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Physics-Informed Neural Networks for Two-Phase Flow Simulations: An Integrated Approach with Advanced Interface Tracking Methods

Wen Zhou, Shuichiro Miwa, Koji Okamoto

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Cooperative Nuclear Safety Research Activities at the Nuclear Energy Agency in Response to the Fukushima-Daiichi Accident

Yuji Kumagai, Didier Jacquemain

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Hydraulic experiments on a 1/5 Scale Model of APR1000 reactor

Kihwan Kim, Woo-Shik Kim, Hae-Seob Choi, Hyosung Seol, Byung-Jun Lim, Dong-Jin Euh

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Validation of Evaluation Model for Thermal Absorber System in High Temperature Gas-Cooled Reactor Nuclear Hydrogen Production System

Takeshi Hasegawa, Takeshi Aoki, Atsushi Shimizu, Hiroyuki Sato

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Application of the GIF Safety Design Criteria and Safety Design Guidelines on Natural Circulation Capability to Next Generation Sodium-Cooled Fast Reactor in Japan

Hidemasa Yamano, Satoshi Futagami, Koichi Higurashi

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Investigating the Influence of PCM Properties, Containment Geometry, and Initial Conditions on the Transient Behavior of a PCM-Based Heat Removal System for Passive Molten Salt Fast Reactor

Jihun Im, Jae Hyung Park, Won Jun Choi, Sangtae Kim, Sung Joong Kim, Younghee Kim, Youngsoo Yoon

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Evaluation of Various Correlations for Direct-Contact Heat Transfer in Dispersed Flow Film Boiling Using DRACCAR Code

Tony Glantz, Juan Estaban Luna Valencia, Alexandre Labergue, Michel Gradeck, A.V.S. Olvieira

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Detailed Assessment of Combustion isk and PAR Efficiency in the Late Phase of a Severe Accident within the European AMHYCO Project

Stephan Kelm, Ahmed Bentaib, Leticia Vitores, Joan Fontanet, Luis Enrique Herranz, Araceli Dominguez-Bugarin, Luis Serra Lopez, Gonzalo Jiminez, Carlos Vázquez-Rodríguez, Michael Klauck, Ludovic Maas

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On Flow Distribution and Heat Transfer in a Graphite Moderated Molten Salt Reactor

Timothy A. Ruscoe, Y. Alatrash, L. Fischer, L. Bureš, Zs. Elter

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Interpretation from Sample Analysis Results Obtained in Fukushima Daiichi NPS to Accident Progressions　-First Trial-

Masato Mizokami, Mutsumi Hirai, Shinya Mizokami, Hirotomo Ikeuchi

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Validation of NEPTUNE_CFD for Single and Two-Phase Natural Convection

Adrien Fayet, P. Boivin, J. Perez Manes, T. Cadiou, S. Mimouni

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Mechanism Study on Condensation Heat Transfer on Shell Side of Spiral Wound Heat Exchanger : Visualization of Film Behavior

Myeonggi Cha, Yongnam Lee, Hang Jin Jo

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Experimental Study of the Effect of the Heating Profile on the Characteristics of the Geysering Instability

K.M. Yassin, Carlos A. Dorao, M. Fernandino

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GAMMA+ Simulation of Turbulent Heat Transfer Over a Backward-Facing Step

S.H. Yoon, Dongyeol Yeo, N.I. Tak, H.S. Lim

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Experimental Investigation of Erosion and Corrosion of Coated and Uncoated Steels Under High Velocity Lead Flow

Celt Llyn Griffith, Charlotte L. Baxter, John Thomas Prabhakar, Walter Villanueva

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Effect of Heater Sizes on Critical Heat Flux and Enhancement using Discretized Heating Elements with Constant Temperature Wall Condition

Seock Yong Lee, Ung Jin Na, Hang Jin Jo

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Large-Scale Ex-Vessel Corium Spreading Calculation Using a Particle Method for Estimating Fuel Debris Distribution in Fukushima Daiichi Unit 1: Effect of Cooling Efficiency on Spreading

Ryo Yokoyama, Shunichi Suzuki, Koji Okamoto, Masahiro Kondo

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Understanding MELCOR CVH/FL Governing Equations for Future AI Applications

Cheolwoong Kim, Jae Hyung Park, Joon Young Bae, Chang Hyun Song, Youngjun Lee, Sung Joong Kim, Jongoo Jeon

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Multi-Scale Coupled Simulation of E-SCAPE at Isothermal Conditions

M.M.M.D. Hussain, Fajar S.L. Pangukir, Dirk C. Visser, M.M. Stempniewicz, Ferry Roelofs, Julio Pacio, Katrien Van Tichelen

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Computational Fluid Dynamics Analysis of the Core of the Motel Facility

Nazia Rahim Anaya, Giteshkumar Patel, Joonas Telkka, Juhani Hyvarinen

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Flow-Induced Vibrations in Nuclear Steam Generators: Simulation of the AMOVI Experiment with Different FSI Approaches

Angel Papukchiev, Hemish Mistry, Joachim Herb

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Application of Risk Informed Safety Margin Characterization to the Analysis of a Pressurized Water Reactor

Y.M. Chen, D.W. Wu, T.C. Wang, M. Lee

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Initial Results of Scaled MHTGR Lower Plenum CFD Analysis

Benjamin Nakhinikian-Weintraub, Izabela Gutowska, Brian G. Woods

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Thermal-Hydraulic Simulations of Turbulent Flows using the Immersed Boundary Method for Innovative Nuclear Reactor Safety Devices

Michel Belliard

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Critical Review of the Film Flow Model by Okawa et al.: Analysis and Improvement Potentials

Sebastian Leopoldus, Michael Buck, Jorg Starflinger, Laura Licht

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Analysis of the Metal Containment Vessel Wall Thickness Effect on the Coolability of the Flooding Safety System using the MELCOR Code

Hyo Jun An, Jae Hyung Park, Jin Ho Song, Sung Joong Kim

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Experimental Investigation of Flow Boiling Regimes in a Horizontal Heated Pipe

Carlos A. Dorao, Maria Fernandino

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Experimental Study on Pool Boiling of Aqueous Surfactant Solutions on Micro-Structured Surfaces for Boiling Enhancement

Song Ni, Chung Ki Cheng, Jiyun Zhao

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Development of a Flow Boiling Heat Transfer Correlation for a Helically Coiled Tube

Min Gi Kim, Byongjo Yun, Jae Jun Jeong

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IAEA Benchmark CRP - I31038: Open Phase Liquid-Metal CFD Results for Fuel Pin Simulator

Abdalla Batta, Andreas Class

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Experimental Investigation of Two-Phase Flow Instability in HTR-10 Steam Generator

Yang Su, Hongyi Fan, Xiaowei Li, Xinxin Wu, Libin Sun

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The Conceptual Design of Integrated Emergency Operating Procedures with Hierarchical Structure

Jung Sung Kang, Seung Jun Lee

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Development of Reactor Vessel Thermal–Hydraulic Analysis Method in Natural Circulation Conditions - Investigation of Interwrapper Gap Model -

Erina Hamase, Norihiro Doda, Ayako Ono, Masaaki Tanaka, Y. Miyake, Y. Imai

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Source Term Assessment and Preparation of Countermeasures in Fukushima Daiichi NPS Unit-1 in Case of Further Degradation of Support Function of Pedestal Caused by Earthquakes

Daisuke Yamauchi, Kazutaka Mogi, Kento Sawada, Shinya Mizokami, Yuichi Iwata

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Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (4) Analyzing Eutectic Melting and Relocation Dynamics in B4C-Stainless Steel Using the Moving Particle Semi-Implicit (MPS) Method

Z. Ahmed, S. Wu, M. Pellegrini, K. Okamoto, K. Sharma, H. Yamano

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Experimental Investigation of Critical Heat Flux and Post-Critical Heat Flux in a Carbon Dioxide Cooled Tube at High Subcritical Pressures.

Jakub Bronik, Michael Buck, Jorg Starflinger

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The Preliminary Analysis of a Typical Fluoride-Salt-Cooled High-Temperature Reactor in the Loss of Flow Accident with the Influence of Rolling Motion

Limin Liu, Jiaming Zhang, Ziyin Liu, Ziang Guo, Hanyang Gu

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BWRX-300’s Nominal Pressure and Temperature Testing (2): Steam-Water Two-Phase Flow Evaluations in Large Diameter Chimney Based on Void Fraction Measurement using Double-Plane Wire-Mesh Sensor

Hajime Furuichi, Antonin Povolny, Kenichi Katono, Kenichi Yasuda, Kazuaki Kito, Charles Heck

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Steam Generator Model Design Parameter Sensitivity Study Using Machine-learning Tools

Palash K. Bhowmik, Tejas Kedlaya, Congjian Wang, Piyush Sabharwall

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BWRX-300’s Nominal Pressure and Temperature Testing (1): Analysis of Test Results from Various Large Diameter Chimney Tests at Elevated Pressure and Temperature

Antonin Povolny, Hajime Furuichi, Kenichi Katono, Kenichi Yasuda, Kazuaki Kito

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Modeling the Impact of Surface Characteristics on Wall Boiling Performance in Subcooled Flows

Alice Ding, Gustavo Aguiar, Matteo Bucci, Emilio Baglietto

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First Steps in Developing a Sampling-based Approach to Incorporate Uncertainties in CFD Modeling of Involute Fuel Element Research Reactors

Ronja Schonecker, Paolo Bianchini, F. Thomas, Y. Calzavara, Winfried Petry, Christian Reiter

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An Approach to Establishing Operator Trust Through an Explainable Diagnostic Model

Ji Hyeon Shin, Seung Jun Lee

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Wall-Modelled Large Eddy Simulation (LES) for the Separated Effect Flow Accelerated Corrosion and Erosion (SEFACE) Facility

Kin Wing Wong, Ignas Mickus, Sumathi Vasudevan, Dmitry Grischenhko, Pavel Kudinov

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