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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Full Issue
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Page 0
Some CEA Research Activities in Support of Fukushima Daiichi Fuel Debris Retrieval
C. Journeau, V. Bouyer, A. Denoix, A. Bachrata, L. Brissonneau (CEA, DES, IRESNE, DTN, SMTA)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 22-32
Measurements of Boiling Two-Phase Flow Dynamics in a Heated Tube Using Neutron Transmission Imaging
Daisuke Ito, Naoya Odaira, Kei Ito and Yasushi Saito (Kyoto University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 36-44
Optical Fiber Temperature Sensor Performance Test in a Metallic Capillary Tube at High Temperatures
Christopher Balbier, Scout Bucks, Erik Hisahara, Saya Lee, and Federico Scurti (Pennsylvania State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 45-55
Advancements in High-Temperature Measurement Techniques to Aid the Development and Enhance Monitoring of Advanced Reactors
Matthew Leoschke, Christopher Balbier, Scout Bucks, Saya Lee, and Federico Scurti (Pennsylvania State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 56-63
Thermal-Hydraulic Simulations of Turbulent Flows Using the Immersed Boundary Method for Innovative Nuclear Reactor Safety Devices
Michel Belliard (CEA, DES, IRESNE, SESI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 66-77
Long Straight Closed Two-Phase Thermosiphons - Experiments of IKE and Validation of ATHLET models
M.Kirsch, S.I. Cáceres Castro, R. Kulenovic, J. Starflinger (Universität Stuttgart Institut für Kernenergetik und Energiesysteme (IKE))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 78-95
Data-Driven Prediction of Preheater Steady-State Conditions Based on Support Vector Regression
Xubin Wu, Wentao Hao, Wenwen Zhang, Zhenlei Liu, and Weihua Li (Tsinghua University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 96-107
Modeling of Vapor Mass Formation Under Forced Convective Boiling Condition
A. Ono and H. Yoshida (Japan Atomic Energy Agency)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 110-120
Critical Review of the Film Flow Model by Okawa et al.: Analysis and Improvement Potentials
Sebastian Leopoldus, Michael Buck, and Jörg Starflinger (University of Stuttgart)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 121-134
Experimental Study on Pool Boiling of Aqueous Surfactant Solutions on Micro-Structured Surfaces for Boiling Enhancement
Song Ni, Chung Ki Cheng, Jiyun Zhao (City University of Hong Kong)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 135-146
Development of a Saturated Boiling Heat Transfer Correlation for a Helically Coiled Tube
Min Gi Kim, Byongjo Yun, Jae Jun Jeong (Pusan National University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 147-156
Experimental Investigation of Critical Heat Flux and Post-Critical Heat Flux in a Carbon Dioxide Cooled Tube at High Subcritical Pressures
Bronik J, Buck M, and Starflinger J (University of Stuttgart)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 157-171
Modeling the Impact of Surface Characteristics on Wall Boiling Performance in Subcooled Flows
Alice Ding, Gustavo Aguiar, Matteo Bucci, Emilio Baglietto (Massachusetts Institute of Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 174-185
Investigating Post-CHF Heat Transfer Behavior During Dryout and Rewet Cycles
Joon Hyuck Moon, Mohammad Amer Allaf, Juliana Pacheco Duarte (University of Wisconsin-Madison)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 186-197
Experimentation and Modeling of Subcooled Flow Boiling from the Perspective of Large Bubble Formation
Tomio Okawa, Thanh-Binh Nguyen, Ryoma Tsujimura (The University of Electro-Communications)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 198-209
Mechanistic Modeling of Departure from Nucleate Boiling in Subcooled Flow Boiling at Near-Critical Pressure Conditions
L. Licht, M. Westermeier , C. Schifflechner and H. Spliethoff (Technical University of Munich)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 212-223
PLAID Approach for Direct Numerical Simulation of Boiling Phenomena
Nicholas J. Mecham and Igor A. Bolotnov (North Carolina State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 224-233
Mechanism Study on Condensation Heat Transfer on Shell Side of Spiral Wound Heat Exchanger : Visualization of Film Behavior
Myeonggi Cha, Yongnam Lee, and HangJin Jo (Pohang University of Science and Technology )
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 234-242
Experimental investigation of Flow Boiling Regimes in a Horizontal Heated Pipe
C.A. Dorao and M. Fernandino (Norwegian University of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 243-253
Evaluation of Various Correlations for Direct-Contact Heat Transfer in Dispersed Flow Film Boiling Using DRACCAR Code
J.E. Luna Valencia, T. Glantz (Institut de Radioprotection et de Sûreté Nucléaire (IRSN))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 256-267
Experimental Investigation of Phenomena in Heat Transfer to Water at Near Critical Pressures
J. Oettig , L. Licht , T. Ferrand , M. Westermeier , C. Schifflechner , H. Spliethoff (Technical University of Munich)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 268-279
Computation of the 1D Drift Flux Model Parameters in the DEBORA Databank
Paul Rival, Fabrice François, and Vincent Faucher (CEA, DES, IRESNE)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 280-292
Development of a Condensation Model for Realistic Analysis of Heat Removal Behavior by Passive Heat Sinks Within a Containment
Jia Yu, Yeon-Gun Lee (Sejong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 293-303
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, and Pavel Kudinov (KTH Royal Institute of Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 306-318
Evaluation of Interface Capturing Schemes of VOF Method Through Application to Bubble Flows with Single Orifice
Fukuda T, Yamashita S, and Yoshida H (Japan Atomic Energy Agency)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 319-330
Initial Results of Scaled MHTGR Lower Plenum CFD Analysis
Benjamin Nakhnikian-Weintraub, Izabela Gutowska, Brian Woods (Oregon State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 331-342
A Three-Dimensional Multiphysics CFD Analysis of Cobalt Adjuster Units in CANDU Reactors – In Core Operation
Assem Elzaabalawy, Ahmed Elkholy, Mohamed Aboulella, Qasim Khan, and Waleed Mekky (Next Structural Integrity (NSI) Inc.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 343-352
Verification and Validation of RANS Models For Triple Channel Mixing Flows
Evan R. Bures, Abdullah G. Weiss (NIST Center for Neutron Research)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 353-362
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, and Waleed Mekky (Next Structural Integrity (NSI) Inc.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 364-370
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 (Sejong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 371-378
Computational Fluid Dynamics Analysis of Phase One of the OECD-NEA Benchmark on CANDU Thermal-Hydraulics
D. Holler, J. Geymer, M. Avramova (North Carolina State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 379-390
Interface Resolved Simulation of Two-Phase Flow Within a Steam Separator Geometry
Taylor Grubbs, Iffat Faizee, Igor Bolotnov (North Carolina State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 391-401
IAEA Benchmark CRP - I31038: Open Phase Liquid-Metal CFD Results for Fuel Pin Simulator
Abdalla Batta, Andreas Class (Karlsruher Institut für Technologie (KIT))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 402-409
Study of Turbulence and Pressure Recovery in Heat Pipe Vapor Flow Using the Spectral-Element Method
Carolina Bourdot Dutra, Tri Nguyen and Elia Merzari (Pennsylvania State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 412-423
Numerical Investigation of Surface Tension and Orifice Shape Effects on Bubble Injection Dynamics Using Direct Numerical Simulation
Farid Ahmed (University of Illinois at Urbana Champaign)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 424-435
Assessment of Particle Size Distribution Models in STAR-CCM+ and OpenFOAM
Brandon Aranda, Emilio Baglietto (Massachusetts Institute of Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 436-449
On the Influence of Model Uncertainty in Thermal Stratification Simulations of Pool-Type Sodium-Cooled Fast Reactors Using Computational Fluid Dynamics
Yu-Jou Wang and Emilio Baglietto (Massachusetts Institute of Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 450-461
Coupled CFD-STH Modelling of the ATHENA Lead-Cooled Pool Type Facility
P. Cioli Puviani, R. Zanino (NEMO Group, Dipartimento Energia, Politecnico di Torino)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 464-475
Multi-Scale Coupled Simulation of E-SCAPE at Isothermal Conditions
M. M. M. D. Hussain, F. S. L. Pangukir, D. C. Visser, M. M. Stempniewicz, F. Roelofs (Nuclear Research and Consultancy Group (NRG))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 476-488
Flow-Induced Vibrations in Nuclear Steam Generators: Simulation of the AMOVI Experiment with Different FSI Approaches
Angel Papukchiev, Hemish Mistry, Joachim Herb (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 489-503
Comparison of URANS and LES Predictions for the Open Phase of the OECD NEA CSNI Fluid Structure Interaction CFD Benchmark
Graham Macpherson, David Munn, Alan Johnson (Frazer-Nash Consultancy)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 504-515
Coupled Thermal-Hydraulics and Neutronics Simulation Using Sub-Channel CFD and SERPENT
Bryan Tan, Yu Duan, Matthew D Eaton, Michael J Bluck (Imperial College London)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 516-528
Transient Reactor Core Behavior by Multi-Physics Approach with Neutron Kinetics, Fuel Performance and Sub-Channel Thermal-Hydraulics Coupling
Jae Ryong Lee, Han Young Yoon (Korea Atomic Energy Research Institute)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 530-540
Numerical Investigation on Gas and Powder Flow Characteristics of Pebble Bed of Fusion Blanket
Jian Wang, Mingzong Liu (Anhui University of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 541-551
Coupled Computational Fluid Dynamics (CFD) and Finite Element (FE) Thermal Stress Analysis of Thermal Fatigue Phenomena Within a T-junction
Lampunio L, Duan Y, Eaton M D, Bluck M J, Davies C M, Sergis A, Hardalupas Y (Imperial College London)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 552-563
Uncertainty Quantification (UQ) for the Analysis of Thermal Stresses Within a T-junction Pipe Wall Using a Structured Gaussian Process (GP) Method
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 564-575
COAL Reflooding Experiments During a Loss Of Coolant Accident : Effect of the Water Flow Rate and the Residual Power with Ballooned Rods
Repetto G, Grando Q, Eymery S (Institut de Radioprotection et de Sureté Nucléaire)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 578-589
Loss-of-Heat-Sink Transient Simulation with RELAP5/Mod3.3 Code for the ATHENA Facility
T. Del Moro, F. Giannetti (Sapienza University of Rome)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 590-602
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 (Korea Atomic Energy Research Institute)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 603-610
Experimental Investigation on Intermittent Gas-Liquid Two-Phase Flow Approaching Tube Bundle
Yoshiteru Komuro , Naotaka Uchimichi, Kosuke Shimizu, Shingo Nishida (Research and Innovation Center, Mitsubishi Heavy Industries)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 611-619
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 (Pennsylvania State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 622-633
Integral Effect Test on Intermediate Break Loss-of-Coolant Accident with Coupling RCS and Containment in ATLAS-CUBE Facility
Byoung-Uhn Bae, Jae Bong Lee, Yusun Park, Seok Cho, Jun-Yeong Jung, Kyoung-Ho Kang (Korea Atomic Energy Research Institute)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 634-644
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 (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 645-656
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 (Lanzhou University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 658-666
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 (KTH Royal Institute of Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 667-675
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 , H.S. Yu , Y.H. Jeong (Korea Advanced Institute of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 676-685
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
K. Shehu, D. Bonete Wiese, T. Chemnitz, Ch. Reiter (Forschungs-Neutronenquelle Heinz Maier-Leibnitz)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 690-702
Computational Fluid Dynamics Investigation of a Single CANDU 37M Fuel Bundle Sitting in a 6% Crept Pressure Tube
Z. Lu, M.H.A. Piro (McMaster University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 703-713
Computational Fluid Dynamics Analysis of the Core of the MOTEL Facility
Nazia Rahim Ananya (University of Stuttgart)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 714-725
GAMMA+ Simulation of Turbulent Heat Transfer over a Backward-Facing Step
S. H. Yoon, D. Y. Yeo, N. I. Tak, H. S. Lim (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 728-739
Numerical Codes Validation of Liquid Droplet Entrainment During Reflood via NRC/PSU RBHT Tests
Yue Jin (University of Missouri)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 740-750
Comparative Study of Cold Ramp Tests Simulations with the Thermo-Mechanical Code TESPA-ROD and the Subchannel Code CTF
Y. Périn, J. Sappl (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 751-761
Validation of Dynamic Analysis Code for High Temperature Gas-Cooled Reactor Connecting Hydrogen Production System with a Heat Removal Fluctuation Mitigation System
Takeshi Hasegawa, Takeshi Aoki, Atsushi Shimizu, Hiroyuki Sato (JAEA)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 762-773
Validation of the System Code CATHARE3 on Critical Flow Experiments in the Framework of the OECD-NEA ATRIUM Project
Alberto Ghione, Lucia Sargentini, Guillaume Damblin, Philippe Fillion (CEA)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 776-787
A New Gap Conductance Model for the ATHLET System Code
Vincenzo Anthony Di Nora, Philipp Schöffel, Thorsten Hollands (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 788-799
First Steps in Developing a Sampling-Based Approach to Incorporate Uncertainties in CFD Modeling of Involute Fuel Element Research Reactors
R. Schonecker, W. Petry, C. Reiter (Technical University of Munich)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 800-811
Assessment of Two-Phase Flow Predictability of 3D Components in MARS-KS and TRACE in Rod Bundle Geometry
Yun Seok Lee, Taewan Kim (Incheon National University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 814-825
Evaluation and Demonstration of Predictive Capability Maturity Quantification (PCMQ) Method for Assessing Software Validation and Applicability
J. Lane, P. Gorman, A. Alfandi, T. Moore (Numerical Advisory Solutions)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 826-837
CSNI Code Validation Matrix (CCVM) Current Status and Development Needs
F. Mascari (ENEA)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 838-849
Experimental Study on Single/Two-Phase Flow and Pressure Drop Characteristics in Stratified Porous Bed
Aimad Bouloudenine, Liangxing Li, Zutao Xiang, Shang Shi, Muhammad Abu Bakar (Xi’an Jiaotong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 852-862
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 (CEA Cadarache, DES/IRESNE/DER)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 864-875
Opportunities & Challenges for Two-Phase Flow Microchannel Heat Sinks in Nuclear Systems
N. LeFrancois, R.C. Bowden, S.K. Yang (Canadian Nuclear Laboratories)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 876-887
Numerical Study on Thermal-Hydraulic Characteristic and Performance of 3-D Printed Circuit Heat Exchanger Channel Having Swirling Flow
Seong Min Shin, Su Won Lee, Sungkun Chung, Namhyeong Kim, HangJin Jo (Pohang University of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 888-901
Preliminary Study on the Coupling of Organic Rankine Cycle with the Nuclear Heating Reactor
De-en Song, Wenwen Zhang, Wentao Hao, Weihua Li, Wei Peng (Tsinghua University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 902-914
Validation of NEPTUNE_CFD for Single and Two-Phase Natural Convection
A.Fayet, J.Perez Manes, T.Cadiou (CEA, DES, IRESNE, DER, SESI, LEMS)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 916-928
Simulation of Pressurized Conduction Cooldown in a Scaled High Temperature Gas Reactor Experiment using GOTHIC
T.M. Moore, J.W. Lane (Numerical Advisory Solutions)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 929-940
Thermal hydraulic Analysis of the AP1000 Passive Containment Cooling System Following LBLOCA Using ANSYS FLUENT
Hossam H. Abdellatif, David Arcilesi (University of Idaho)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 941-952
Subchannel Simulation of Rod-Bundle Two-Phase Flow Experiments with Flica5
Xavier Manchon, Théotime Le Borgne de Palfray, Ianis Cosnier (CEA)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 954-966
Void Redistribution Measurement Downstream of Part-Length Rods in Rod Bundle with High-energy X-Ray CT
T. Arai, A. Ui, M. Furuya, R. Okawa, T. Iiyama, S. Ueda, K. Shirakawa (Central Research Institute of Electric Power Industry)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 967-976
Numerical Study on Subcooled Boiling and CHF Phenomenon in Eccentric Annular Channels
Yuanjie Zhang, Bin Han, Xiaoliang Zhu, Guangwei Hong, Tianyang Xing, Siwei Qi, Shenghui Liu (Southeast University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 977-988
Three-Field MEFISTO-T Subchannel Analysis Code Calibration and Applications to CANDU Fuel Thermal-hydraulic Simulations
Jean-Marie Le Corre (Westinghouse Electric Sweden AB)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 989-1001
3D Modeling of Passive Safety Condensers with CATHARE3 for a High-Power Pressurized Water Reactor
Michel Belliard, Lucie Groussy (CEA, DES, IRESNE, SESI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1004-1015
Steam Condensation in Mini-Channels: A Benchmark of Available Correlations
Julie Jambert, Léa Pillemont (ENSEEIHT)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1016-1028
Examination of the Reason Why Hydrogen Explosion did not Occur at Fukushima Daiichi NPP Unit-2
Penghui Chai, Kenichiro Nozaki, Shoichi Suehiro (Tepco Systems Corporation)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1029-1040
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 (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1041-1052
Challenges Regarding the Experimental Validation of Thermal-Hydraulic Modeling Tools for a European SMR
Ignacio Guirado, Andrea Missaglia, Stefano Lorenzi, Marco E. Ricotti (Politecnico di Milano)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1054-1065
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, JinHo Song, Sung Joong Kim (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1066-1076
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 (Becker Technologies GmbH)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1077-1088
System-Level Thermal-Hydraulics Analysis of the Proposed NIST Neutron Source Design
Anil Gurgen, Abdullah G. Weiss (NIST Center for Neutron Research)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1090-1098
Investigation of Effect of Metal Containment Vessel Wall Thickness on Initial Decay Heat Removal with Flooding Safety System using MELCOR Code
Hyo Jun An, Jae Hyung Park, JinHo Song, Sung Joong Kim (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1099-1110
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 (Hitachi-GE Nuclear Energy, Ltd)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1111-1124
BWRX-300’s Nominal Pressure and Temperature Testing (1): Analysis of Test Results from Various Large Diameter Chimney Tests at Elevated Pressure and Temperature
Povolny A, Furuichi H, Katono K, Yasuda K, Kito K (Hitachi-GE Nuclear Energy, Ltd.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1125-1137
Quenching Tempuratures During Reflood Transients in a Rod Bundle
Turki K. Almudhhi, Ian R. Lowery ,Douglas J. Miller, Fan-Bill Cheung (Pennsylvania State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1140-1151
Numerical Modeling of the Two-Phase Critical Flow in a Steam Generator Guillotine Tube Rupture Scenario
Giteshkumar Patel, Lauri Pyy, Sharandeet Singh, Andrei Zaitsev, Juhani Hyvärinen (Lappeenranta-Lahti University of Technology LUT)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1152-1162
Experimental Study of the Effect of the Heating Profile on the Characteristics of the Geysering Instability
Yassin K.M., C.A. Dorao, M. Fernandino (Norwegian University of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1163-1172
Two-phase flow interfacial structure in CANDU reactor fuel channel and feeder pipe under postulated accident conditions
Z. Dang, L. Yuan, J. Yang, L. Li (Canadian Nuclear Laboratories)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1173-1184
Experimental Investigation on Helium Drag Effect in terms of Natural Circulation Enhancement for Passive Molten Salt Fast Reactor (PMFR)
Won Jun Choia, Jae Hyung Parka, Seung Gyu Hyeona, Jinho Songa, Sung Joong Kima (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1185-1194
Nuclear Power Plant Condenser Improvement
P. Tang, A. Bhatia, L. Cramer (Bruce Power Ltd.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1198-1209
Numerical Investigations of Ball Valve Performance in Variable Valve Diameters, Openings and Flow Regimes
Anutam Bairagi, Minghui Chen (University of New Mexico)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1210-1220
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 (The University of Tokyo)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1221-1231
The Conceptual Design of Integrated Emergency Operating Procedures with Hierarchical Structure
Jung Sung Kang, Seung June Lee (Ulsan National Institute of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1234-1244
An Integrated Fiber Optic and Acoustic Leak Detection Technologies for Nuclear Power Plants Water Supply and Reactor Cooling Systems
Eric Yang, Yash Yadav (CARP Associates USA, LLC.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1245-1256
The Impact of Thermal-Hydraulic Information on Nuclear Fission Product Behavior Simulation Using the SIRIUS Module in the CINEMA Code
Yongjun Lee, Chang Hyun Songa, Joon Young Bae, JinHo Song, Sung Joong Kim (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1260-1267
Comparative Analysis of Particle Retention Models in Filtered Containment Venting Systems
Miriam Müer, Marco K. Koch (Ruhr-Universität Bochum (RUB), Plant Simulation and Safety Group (PSS)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1268-1277
CFD Analysis of Hydrogen Within a Filter-Vented Canister Containing Fukushima Fuel Debris
H. Shirai, T. Fujisaki, K. Enomoto, D. Fujiwara (TEPCO Systems Corporation)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1278-1287
Detailed Assessment of Combustion Risk and PAR Efficiency in the Late Phase of a Severe Accident Within the European AMHYCO Project
Stephan Kelm, Michael Klauck, Carlos Vázquez-Rodríguez (Forschungszentrum Juelich)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1288-1301
Modelling and Simulation of Fission Product Release from Melt Pools
Florian Krist, Marco K. Koch (Ruhr-Universität Bochum)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1302-1311
Application of Risk Informed Safety Margin Characterization to the Analysis of a Pressurized Water Reactor
Y. M. Chen (National Atomic Research Institute)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1314-1325
Experimental Validation of Hydrogen Within a Filter-Vented Canister Containing Fukushima Fuel Debris
Martin Plys, Michael Lim, Matthew Kennedy (Fauske & Associates)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1326-1333
Mass and Energy Release Analysis of Postulated Main Steam Line Break Accident for APR1400 Using SPACE-ME Methodology
Jisu Kim, Seong Ho Jee, Sung Yong Kim, Chan Eok Park, Min Shin Jung, Eun Ju Lee, Seok Jeong Park (KEPCO Engineering & Construction Company)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1334-1346
Formation Behavior of Gaseous Iodine from Sodium Iodide Under SFR Severe Accidental Condition
Shin Kikuchi, Toshiki Kondo, Daisuke Doi, Hiroshi Seino (Japan Atomic Energy Agency)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1348-1359
Validation of a Model for Estimating the Retention Efficiency in Pool Scrubbing
Jonas Rehrmann, Tobias Jankowski, Marco K. Koch (Ruhr-Universität Bochum)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1360-1368
MELCOR Model of iPWR and Application to Emergency Planning Zone Study
John Cui, Luke Lebel, Andrew Morreale, David Hummel (Canadian Nuclear Laboratories)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1369-1380
Preliminary Study of Microreactor Emergency Planning Zone
Erik Hisaharaa, Christopher Balbiera, Saya Lee, Rohan Biwalkarb, Sola Talabi (Pennsylvania State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1381-1388
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 (Kyushu University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1390-1401
Severe Accident Analysis of High Pressure Sequences for APR1400 Using CINEMA Computer Code
Rae-Joon Park, Jaehyun Ham, Dong Gun Son, Sangho Kim, Jaehoon Jung (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1402-1413
Preliminary Analysis on Spreading Distance of Spill Molten Salt in MSR for Comparison with Corium in PWR Using Simple Analytical Model
Rae-Joon Park, Jun Young Kang, Sang Mo An, Jun Ho Bae, SungIl Kim (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1414-1422
Source Term Analysis in the Fuel Degradation Phase of PHEBUS FPT-1 Experiment Using MELCOR 2.2
Han Sol Park, Yeon-Gun Lee (Sejong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1423-1434
Cooperative Nuclear Safety Research Activities at the Nuclear Energy Agency in Response to the Fukushima-Daiichi Accident
Yuji Kumagai , Didier Jacquemain (OECD Nuclear Energy Agency)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1436-1444
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, and Koji Okamoto (The University of Tokyo)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1445-1456
Fukushima Daiichi Nuclear Power Plant Accident Analysis Considering the Thermal Stratification and Containment Leakage
Y. Nakamura 1 , Y. Kojima (Toshiba Energy Systems & Solutions Corporation)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1457-1468
Simulation of Transient Melting of CANDU Debris Bed Under Severe Core Damage Accident
Y. Sun, S. Tullis, M. Lightstone (McMaster University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1470-1479
Three-Dimensional Lagrangian-Eulerian Modeling and Analysis of Fuel-Coolant Interaction
Kwang-Hyun Bang (Tetras, Co.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1480-1490
Interpretation from Sample Analysis Results Obtained in Fukushima Daiichi NPS to Accident Progressions -First Trial-
Masato Mizokami, Mutsumi Hirai, Shinya Mizokami (Tokyo Electric Power Company Holdings, Inc.)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1491-1503
Numerical Analysis of In-Vessel Melt Retention of CANDU Reactors During A Severe Accident
S. Gyepi-Garbrah, F. Mehdi Zadeh, B. Moore, T. Nitheanandan (Canadian Nuclear Safety Commission (CNSC))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1504-1520
A Review of Fuel Fragment Jamming Inside Fuel Rods Following a LOCA
Gordon J Wissinger (Framatome Inc)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1522-1532
Approach for Rod Burst Ratio Evaluation During Loss-Of-Coolant Accident with DRACCAR Software
Belon S., Taurines T., Glantz T. (Institut de Radioprotection et de Sûreté Nucléaire (IRSN))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1533-1544
Preparing the MACCS Code for Advanced Reactor Applications
Mariah Garcia (Sandia National Laboratories)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1545-1552
Lessons Learned and Best Practices on BWR Severe Accident Uncertainty and Sensitivity Analysis in the Framework of the IAEA CRP I31033
J. Ortiz-Villafuerte (ININ)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1554-1565
Probabilistic Safety Analysis in Risk Informed and Performance Based Safety Management
Erdal Ozdemir (The University of Tokyo)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1566-1574
IAEA CRP I31033: Severe Accident Uncertainty and Sensitivity Analyses for Reactors of PWR and SMR Types and Relevant Insights
K.I. Ahn (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1575-1586
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
S.M. Petoukhov, A.C. Morreale (CNL)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1587-1600
Severe Accident Analysis of a Generic Small Boiling Water Reactor
Feng Zhou, Andrew C. Morreale, Luke Lebel, John Cui, Garik Patterson (Canadian Nuclear Laboratories (CNL))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1602-1613
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 (The University of Tokyo)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1614-1627
Analysing the Ablation of Concrete, Heat and Mass Transfer During Molten Corium-Concrete Interaction: Impact of Concrete Melting Temperature
Ilyas Khurshid, Yacine Addad, Imran Afgan (Emirates Nuclear Technology Centre (ENTC))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1628-1642
Comparison Between EDF MAAP5.04 and ASTECv3 Codes on Hypothetical Severe Accidents in an Integral PWR
Jeremy Bittan, Nikolai Bakouta (Electricité de France (EDF) Lab Paris-Saclay)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1643-1654
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 (Ruhr-Universität Bochum (RUB))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1658-1668
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 (Karlsruhe Institute of Technology (KIT))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1669-1680
Morphology Change of CRUD Formed on Fuel Cladding by Deposition Time in Pressurized Water Reactor Environment
Yunju Lee, Junhyuk Ham, Junhyuk Jeong, and Ji Hyun Kim (Ulsan National Institute of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1681-1688
Development of Fission Gas Release Modeling in CTF for High Burnup Fuel Transient Analysis
Charles Cheron, Agustin Abarca, Maria Avramova (North Carolina State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1689-1700
Investigation of the Impacts of Downward Reflood Quenching Phenomena on Rod Bundle CHF Measurements and on Safety Margin in LWR type SMRs
Bao-Wen Yang, Stephanie H. Yang, Jeremy Silber (DEQD Delta Energy Group New York (DEGNY/GDES))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1702-1713
Flow Instability Tolerance Simulation Heater for SMR and Other Rod Bundle CHF Tests Under Low Pressure, Low Flow Conditions
Eric Yang, Ray Smith (CARP Associates USA, LLC)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1714-1724
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
T. Hollands (GRS gGmbH)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1725-1733
Establishing a LOCA Fuel Safety Evaluation Methodology for Assessment of Advanced Technology Fuel Performance Using FRAPTRAN-TE-1.5
Jinzhao Zhang, Thomas Drieu (Tractebel (ENGIE))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1734-1745
The Adaptive Residual Differential Physics-Informed Neural Networks for Two-Phase Flow Simulations: An Integrated Approach with Advanced Interface Tracking Methods
Wen Zhou , Shuichiro Miwa , Koji Okamoto (University of Tokyo)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1748-1760
Real-Time Modeling of Gas-Liquid Two-Phase Flow Through Machine Learning and Data Assimilation with Experimental Data
Miki Saito, Taizo Kanai (Central Research Institute of Electric Power Industry)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1761-1769
Reliability and Safety Assessment of Isolation Condenser System in BWRX-300
Saikat Basak, Lixuan Lu (Ontario Tech University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1770-1779
Evaluation of Physics-Informed Machine Learning Models for Liquid Entrainment During Reflood Transient Using NRC/PSU RBHT Data
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1780-1791
Potential Applications and Recommendations of Dynamic Event Tree Analysis Using DICE(Dynamic Integrated Consequence Evaluation)
Gyunyoung Heo, Dohun Kwon, Yuntae Gwak, Yongjoon Lee (Kyung Hee University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1794-1801
Prediction of Single Channel Critical Heat Flux by Machine Learning Approaches
Yen-Hsun Wang, Yang-Cheng Shih, Cheng-Chuan Lin (National Taipei University of Technology (NTUT))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1802-1811
An Approach to Establishing Operator Trust Through an Explainable Diagnostic Model
Ji Hyeon Shin, Seung Jun Lee (Ulsan National Institute of Science and Technology)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1814-1822
Advanced Thermal Monitoring in Scaled Reactors Using Deep Learning-Enhanced Drone IR Imaging
Do Yeong Lim, Ik Jae Jin, In Cheol Bang (Ulsan National Institute of Science and Technology (UNIST))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1823-1832
Understanding MELCOR CVH/FL Governing Equations for Future AI Applications
Cheolwoong Kim , Jae Hyung Park, Joon Young Bae, Chang Hyun Song, Yongjun Lee, Sung Joong Kim (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1833-1842
A Novel Approach for Parametric Dynamic Mode Decomposition: Application to the DYNASTY Experimental Facility
Stefano Riva, Andrea Missaglia, Carolina Introini, Antonio Cammi (Politecnico di Milano, Department of Energy)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1843-1854
Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents
Semin Joo, Yeonha Lee, Seok Ho Song, Jeong Ik Lee (Korea Advanced Institute of Science and Technology (KAIST))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1855-1862
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 (Canadian Nuclear Laboratories)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1864-1875
ARIANT and RELAP5-3D Simulation of OECD-NEA Benchmark Against the Oregon State University High Temperature Test Facility Data
X. Huang, T. Jafri, G. Waddington (Canadian Nuclear Laboratories)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1876-1888
Designs of Printed Circuit Steam Generator for the Modular Integrated Gas-Cooled High Temperature Reactor
Haekyun Park, Chengqi Wang, Xiaodong Sun (University of Michigan)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1889-1901
Towards CFD Modelling of the Lower Plenum Mixing Test of the OSU High Temperature Test Facility
M. M. M. D. Hussain, F. Roelofs (Nuclear Research and Consultancy Group (NRG))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1902-1914
Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (1) Project Overview and Progress Until 2022
H. Yamano , T. Takai, and Y. Emura (Japan Atomic Energy Agency (JAEA))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1916-1927
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
T. Takai, Y. Emura, H. Yamano (Japan Atomic Energy Agency (JAEA))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1928-1938
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
K. Morita (Kyushu University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1939-1946
Development of Reactor Vessel Thermal–Hydraulic Analysis Method in Natural Circulation Conditions - Investigation of Interwrapper Gap Model -
E. Hamase, N. Doda, A. Ono, M. Tanaka (Japan Atomic Energy Agency)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1947-1958
Experiments and CFD for Wire-wrapped Fuel Assembly Blockages
Ferry Roelofs, Akshat Mathur, Heleen Uitslag-Doolaard (NRG)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1960-1971
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 (Japan Atomic Energy Agency (JAEA))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1972-1983
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, M. Avramova (North Carolina State University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1984-1993
Comparison of System Thermal Hydraulic and CFD Analyses of NACIE-UP Asymmetric Test
F. S. L. Pangukir, A. Mathur, M. M. Stempniewicz, F. Roelofs (Nuclear Research and Consultancy Group (NRG))
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1994-2005
Assessment of the Rankine Vortex Model for Modeling the Gas Entrainment in a Representative Mock-up of a Sodium Fast Reactor
Guenadou D, Aubert P, Descamps J-P (CEA, DES, IRESNE, Nuclear Technology Department, Center of Cadarache)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2008-2017
Development of a Source Terms Migration Model for CDA Bubble
Zeren Zou, Wei Liu, Koji Morita (Kyushu University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2018-2029
Experimental Investigation of Erosion and Corrosion of Coated and Uncoated Steels Under High Velocity Lead Flow
Celt Llŷn Griffith, Charlotte L. Baxter, John Thomas Prabhakar, Walter Villanueva (Bangor University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2030-2040
Code Analyses on PDHRS Performance and Unprotected Loss of Flow Scenario for a Sodium-cooled Fast Reactor of SALUS
Hyun-Sik Park, Sun-Rock Choi, Junkyu Han, Jonggan Hong (Korea Atomic Energy Research Institute)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2041-2053
Conceptual design and preliminary analysis of the heat pipe cooled reactor-battery hybrid energy system
Limin Liu, Ziyin Liu, Ziang Guo, Hanyang Gu (Shanghai Jiao Tong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2056-2065
Investigation of Thermal Limitations in Heat Pipes Using Three Different Working Fluids in a Heat Pipe Reactor
Gizem Bakir (Canadian Nuclear Safety Commission)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2066-2075
Preliminary Analysis of Flow Distribution in a 100-MWth Molten Salt Fast Reactor Core with Flow-Guide Structures Using Computational Fluid Dynamics
Dongyeol Yeo, Si Hwa Jeong , Chan Lee, Gyeong-Hoi Koo (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2078-2089
Development of Data-Driven Eddy Viscosity Closure to Support MSR Flow and Heat Transfer Modeling Based on SAM-ML
Yang Liu (Texas A&M University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2090-2101
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 (CEA, DES, IRESNE, DEC)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2102-2116
On Flow Distribution and Heat Transfer in a Graphite Moderated Molten Salt Reactor
T. A. Ruscoe, Y. Alatrash, L. Fischer, L. Bureš, Zs. Elter (Seaborg Technologies Aps)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2118-2129
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 (Shanghai Jiao Tong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2130-2144
Development of an Advanced Freeze Valve System for Molten Salt Reactor
Chan Lee, Dongyeol Yeo, Yun Bum Park, Gyeong-Hoi Koo (KAERI)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2145-2154
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 (Hanyang University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2155-2170
Novel Approach for Modeling Effective Delayed Neutron Fraction and Transient Reactivity Feedback Effects for Circulating Fuel Reactors
J. Lane, T. Moore (Numerical Advisory Solutions)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2171-2182
A Novel OpenFOAM Library for Magneto-Hydrodynamics Studies in the Nuclear Fusion Field
Matteo Lo Verso, Carolina Introini, Eric Cervi, Francesca Giacobbo, Antonio Cammi (Politecnico di Milano)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2184-2195
Intelligent Control System Design for Implementation of Control Strategies for Supercritical CO2 Brayton Cycle-Cooled Reactor System
Ghulam Jillani, Jianqiang Shan, Wu Pan (Xi’an Jiaotong University)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 2196-2207
