SPH Simulation on Single Bubble Behavior in Linear Shear Flow (English)
- New search for: Ahn, Yelyn
- New search for: Jo, Young Beom
- New search for: Park, So Hyun
- New search for: Kim, Jin Woo
- New search for: Kim, Eung Soo
- New search for: Ahn, Yelyn
- New search for: Jo, Young Beom
- New search for: Park, So Hyun
- New search for: Kim, Jin Woo
- New search for: Kim, Eung Soo
In:
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9
; 3820-3832
;
2020
- Conference paper / Print
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Title:SPH Simulation on Single Bubble Behavior in Linear Shear Flow
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Contributors:Ahn, Yelyn ( author ) / Jo, Young Beom ( author ) / Park, So Hyun ( author ) / Kim, Jin Woo ( author ) / Kim, Eung Soo ( author )
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Conference:NURETH ; 18. ; 2019 ; Portland, Or.
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Published in:
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Publisher:
- New search for: Curran Associates, Inc.
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Place of publication:Red Hook, NY
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Publication date:2020
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Type of media:Conference paper
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Type of material:Print
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Language:English
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Source:
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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Remaining Issues in System Thermal Hydraulics How the Fonesys and CONUSAF Networks Can Help Find Solutions?Bestion, D. / d’Auria, F. / Hassan, Y. / Aksan, N. / Lanfredini, M. / Kim, K. D. et al. | 2020
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A New Approach of Studying Transient Critical Heat Flux Using Computational Fluid DynamicsChen, T. / Marcum, Wade et al. | 2020
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A New Hypothesis of Transient Boiling Based on the CFD Simulation and Past Experimental StudiesChen, T. / Marcum, W. et al. | 2020
- 3820
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SPH Simulation on Single Bubble Behavior in Linear Shear FlowAhn, Yelyn / Jo, Young Beom / Park, So Hyun / Kim, Jin Woo / Kim, Eung Soo et al. | 2020
- 3833
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Improved Design of Spent Fuel Dry Storage Using Phase Change Heat Transfer of Hybrid Control Rod-Heat PipeKim, Kyung Mo / Bang, In Cheol et al. | 2020
- 3844
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Experimental Investigation on Atmospheric, Passive Spent Fuel Pool Cooling by Two-Phase Closed ThermosyphonsGrass, Claudia / Kulenovic, Rudi / Starflinger, Jöerg et al. | 2020
- 3856
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Buoyancy-Driven Transformations in a Thermal Striping Flow FieldLomperski, S. / Merzari, A. Obabko E. et al. | 2020
- 3865
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Thermal Hydraulic Design of an In-Pile Experimental Loop for Fast Test Reactor ConditionsHiggins, Anton / LaBrier, Dan / Marcum, Wade / Lilley, Ben / Palmer, Todd et al. | 2020
- 3879
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Computational Fluid Dynamics Assessment of Proposed Axial Reflector Designs for the Versatile Test Reactor Using Nek5000Shaver, D. R. / Yuan, H. / Heidet, F. et al. | 2020
- 3893
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Integrated Simulation Capabilities for Thermal Hydraulic Analysis of Test Vehicles in the Versatile Test ReactorBrunett, A. J. / Hua, T. Q. / Hu, G. / Hu, R. / Fanning, T. H. / Zhang, G. et al. | 2020
- 3908
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Transient Analysis of an FHR Coupled to a Helium Brayton Power CycleZhang, Guolei / Chen, Minghui / Sun, Xiaodong et al. | 2020
- 3922
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Molten Salt Coolant Modeling In TRACERoth, Glenn / Spore, Jay et al. | 2020
- 3931
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CFD Simulation of Xenon Removal by Helium Bubble Sparging in Molten SaltChen, Jiagi / Brooks, Caleb S. et al. | 2020
- 3945
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Flow Rates in a Natural Circulation FLiBe LoopBritsch, Karl / Anderson, Mark / Sridharan, Kumar et al. | 2020
- 3955
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Uncertainty Analysis of PIV Measurements for Liquid Velocity in Two-Phase Bubbly FlowsLiu, Yang / Qian, Yalan / Wang, Chengqi / Sun, Xiaodong et al. | 2020
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Characterization of Liquid Jet Breakup for the Simulation of Accidental Sodium Leakage Scenarios in Sodium-Cooled Fast ReactorsSadek, Leakage Mira / Gilardi, Thierry / Bazile, Rudy / Mimouni, Stéphane / Porcheron, Lynda et al. | 2020
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- 3989
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Preliminary Results on the Development of a Fast-Neutron Tomography System for Void Fraction Distribution MeasurementsPatterson, G. G. / Novog, D. R. et al. | 2020
- 4004
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Ex-Vessel Fuel Coolant Interaction Experiment with the Geometry of an AP1000 ReactorAlbrecht, Giancarlo / Meyer, Leonhard / Zhang, Rongjin et al. | 2020
- 4018
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Premixed Laver Formation Modelling in Stratified Melt-Coolant GeometryKokalj, Janez / Leskovar, Matjaz / Ursic, Mitja et al. | 2020
- 4032
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Risk of Containment Failure Due to Ex-Vessel Steam Explosion for Nordic BWRsGrishchenko, Dmitry / Galushin, Sergey / Kudinov, Pavel et al. | 2020
- 4039
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Melt Droplet Fragmentation Behavior During Fuel-Coolant InteractionLi, Gen / Feng, Haobo / Wen, Panpan / Zhang, Jun / Wang, Jinshi / Yan, Junjie et al. | 2020
- 4050
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Dispersion of Surrogate LWR Fuel Experiments Under LOCA ConditionsLatimer, G. D. / Marcum, W. R. / Jones, W. F. et al. | 2020
- 4063
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A Summary of Fission-Product Transport Phenomena During SGTR Severe AccidentsLind, T. / Campbell, S. / Herranz, L. E. / Kissane, M. / Song, JinHo et al. | 2020
- 4076
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Simulation of In-Vessel Retention Scenarios in PWR with ATHLET-CDPandazis, P. / Weber, S. et al. | 2020
- 4087
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- 4098
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Digitilization and Management of Thermal Hydraulic Legacy Data Using FPoliDON PlatformFrepoli, Cesare et al. | 2020
- 4109
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Revisiting the PIRT and Scaling Analysis Within the Frame of 3D System Code ModellingBestion, D. / Fillion, P. et al. | 2020
- 4123
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Application of Adjoint Based Node Optimization Method to Nuclear Thermal-Hydraulic System Analysis CodeLee, Jae Jun / Son, Seongmin / Kim, Min-Gil / Lee, Jeong Ik et al. | 2020
- 4137
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Preliminary Tasks to Integrate CATHARE 2 3D Reactor Vessel Module in Real-Time Simulators at EDF/DTPialla, David / Ludmann, Marc / Vareille, Karine et al. | 2020
- 4150
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A Rotodynamic Pump Seizure Transient Simulated Using the CATHARE-3 Dimensional Pump Model (CEA)Matteo, L. / Mauger, G. / Gyomlai, P. / Dazin, A. / Tauveron, N. et al. | 2020
- 4164
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Multiscale and Multiphysics Simulation of Sodium Fast Reactors: From Model Development to Safety DemonstrationGerschenfeld, Antoine et al. | 2020
- 4178
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Molecular Tagging Velocimetry: Pushing the Limits of VelocimetryBardet, P. M. / Fort, C. / Andre, M. A. et al. | 2020
- 4184
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Overview of Thermal-Hydraulic Validation Tests with SMART-ITL to Support SMART Pre-Project EngineeringPark, Hyun-Sik / Bae, Hwang / Ryu, Sung-Uk / Yang, Jin-Hwa / Jeon, Byong-Guk / Bang, Yoon-Gon / Yi, Sung-Jae et al. | 2020
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Comparison of Two Different Sized Small Break LOCAs on the Passive Safety Injection Line with SMART-ITL (KAERI)Yang, Jin Hwa / Bae, Hwang / Ryu, Sung-Uk / Jeon, Byong Guk / Yi, Sung-Jae / Park, Hyun-Sik et al. | 2020
- 4211
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Hot Spot Temperature Prediction for a Micro Modular High Temperature Cooled Reactor (KAERI)Lee, Sung Nam / Tak, Nam-il / Jo, Chang Keun et al. | 2020
- 4219
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Development of a SCDAP/RELAPS Model for the Simulation of the Helical-Coiled Once-Through Steam GeneratorsXu, Ziyi / Liu, Maolong / Xiao, Yao / Gu, Hanyang et al. | 2020
- 4233
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Flow Dynamic Behavior in Rod Bundles: An Experimental AssessmentNalin, O. C. A. / Lazo, P. / Marcel, C. P. et al. | 2020
- 4246
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Effect of Part-Leneth Rds and Transient Flow for Different BWR Subchannel GeometriesRobers, Lukas / Prasser, Horst-Michael et al. | 2020
- 4260
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Unsteady Pressure and Velocity Measurements in 5x5 Rods Bundle Using with and Without Mixing VanesTurankok, N. / Bazin, F. / Biscay, V. / Lohez, T. / Moreno, F. / Testaniére, S. / Rossi, Lionel et al. | 2020
- 4273
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Experimental Investigation of Power Transient Critical Heat Flux for Downward Flow in Narrow Rectangular Channel Used in Research ReactorKim, Hui Yung / Jeong, Jae Jun / Yun, Byong Jo et al. | 2020
- 4287
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A Three-Dimensional PWR LBLOCA Simulation Using the CUPID CodePark, Ik Kyu / Yoon, Han Young / Lee, Seung Jun / Cho, Yun Je / Lee, Jae Ryong et al. | 2020
- 4299
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- 4310
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Chimney and Diverging Effects in Core PWR: Analysis and Experimental Characterization for Predictive Behaviour During Loss of Coolant AccidentRabe, Christophe / Préa, Raphael et al. | 2020
- 4324
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CFD Analysis of Hydrogen Flame Acceleration with Burning Velocity ModelsMotegi, K. / Trianti, N. / Matsumoto, T. / Sugiyama, T. / Maruyama, Y. et al. | 2020
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Numerical Investigation of the Effect of Buoyancy Forces on the Deflagration of Hydrogen in the THAI FacilityAttavino, A. / Koloszar, L. / Planquart, P. / Adorni, M. / Parente, A. et al. | 2020
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Development of a Radionuclide Release Module for an Integrated Source Term Analysis Tool for Liquid Metal Cooled Fast ReactorsHua, T. Q. / Lee, S. J. / Liao, J. / Moisseytsev, A. / Ferroni, P. / Karahan, A. / Paik, C. Y. / Sofu, T. et al. | 2020
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Numerical Study of Lean Limit Hydrogen Flames Propagating Upward to Validate a Flammability Limit ModelJeon, Joongoo / Jung, Hoichul / Kim, Yeon Soo / Kim, Sung Joong et al. | 2020
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- 4388
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Preliminary RELAPS Svstem Analysis of the Water-Based NSTF — Part 2: Parametric StudyLv, Q. / Kraus, A. / Hu, R. / Bucknor, M. / Lisowski, D. et al. | 2020
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Turbulent Natural Convective Condensation on the Underside of Inclined Surfaces for the AP1000* Plant ContainmentSwartz, Matthew M. / Lojek, John / Wright, Richard F. / Vanston, Ryan T. et al. | 2020
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Onset of Natural Convection in a Sodium-Cooled Fast Reactor During a Station Black-Out: Blind Benchmark of Safety Assessment Using Multi-Scale Coupled Thermal Hydraulics Codes (Framatome)Li, Simon / Gerschendfeld, Antoine / Bernard, Olivier / Sageaux, Thomas et al. | 2020
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Modelling of the DIADEMO Experiment with the CATHARE Code for ASTRID Gas Power Conversion System StudiesMauger, G. / Hochart, M. / Grosjean, B. / Taraud, P. / Morassano, B. et al. | 2020
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Oscillation Phenomenon Study for the Anti-Siphon Equipment in CFR600 DesignPeng, Yan et al. | 2020
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Validating System Analysıs Module (SAM) Models Using Natural Circulation Experimental DataLin, Hsun-Chia / Hu, Rui / Sun, Xiaodong et al. | 2020
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Modelling the Draining of a Molten Chloride Salt ReactorLewis, Emily / Cartland-Glover, Gregory / Rolfo, Stefano / Moulinec, Charles / Emerson, David R. / Merk, Bruno et al. | 2020
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Progess in the Thermal Hydraulic Modeling of the Molten Salt Fast ReactorTano, M. / Rubiolo, P. / Ragusa, J. et al. | 2020
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Measurements of Boiling Heat Transfer, Time-Averaged Void Fraction Distributions Using Neutron RadiographyMuhammad, Abir / Khaykovich, Boris / Petrik, Jan / Kossolapov, Artyom / Phillips, Bren / Bucci, Matteo et al. | 2020
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