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Author Index
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages lii-lxii
A Multi-Scale Approach Simulating Generic Pool Boiling
T. Höehne, D. Lucas (HZDR)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1-13
Numerical Simulations of Turbulent Rayleigh-Bénard Convection with a Free Surface
W. A. Hay (Université Catholique de Louvain), V. Deledicque (Bel V), M. V. Papalexandris (Université Catholique de Louvain)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 14-28
Towards Best Practice Guidelines for Euler-Euler Simulations of Poly-Disperse Bubbly Flows
D. Lucas, Y. Liao, R. Rzehak, E. Krepper (HZDR)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 29-41
Annular Flow Simulation Supported by Iterative In-Memory Mesh Adaptation
J.Fang (ANL), M. K. Purser (Univ of Colorado Boulder), C. Smith (RPI), R. Balakrishnan (ANL), I. A. Bolotnov (NCSU), K. E. Jansen (Univ of Colorado Boulder)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 42-55
Comparative Analysis of Core Degradation Models Between ASTEC and MELCOR. Application to the Fukushima Daiichi Unit-1 Like Accident
P. Drai, C. Bouillet, H. Bonneville, V. Topin, L. Laborde, S. Belon (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 56-71
Analysis for the Accident at Unit 1 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project
Hitoshi Tamaki, Jun Ishikawa, Tomoyuki Sugiyama, Yu Maruyama (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 72-82
Simulation of the Fukushima Daiichi Unit 2 Severe Accident with MELCOR 2.1
A. C. Morreale (CNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 83-99
Analysis for the Accident at Unit 2 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project
Hitoshi Tamaki, Jun Ishikawa, Tomoyuki Sugiyama, Yu Maruyama (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 100-111
Predictive Study of Condensing Vapour Bubble in Subcooled Boiling Flow Using InterSection Marker Method
Syed Ahsan Sharif (UNSW), Mark Kai Ming Ho (ANSTO), Victoria Timchenko (USW), Guan Heng Yeoh (USW/ANSTO)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 112-126
Applying Tet-to-Hex Meshing Method to Complex Nuclear Reactor Geometries for Spectral Element Code
Haomin Yuan, Elia Merzari, Yiqi Yu, Aleksandr Obabko (ANL), Mustafa A. Yildiz, Gerrit Botha, Yassin A. Hassan (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 127-135
Evaluation of Turbulence Modeling Approaches for the Prediction of Cross-Flow in a Helical Tube Bundle
Jinyong Feng, Michael Acton, Emilio Baglietto (MIT), Adam R. Kraus, Elia Merzari (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 136-148
Particle Decontamination in a Single Bubble During Pool Scrubbing
K. Fujiwara, Y. Nakamura, A. Kaneko, Y. Abe (Univ of Tsukuba)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 149-159
Heat Loss Assessment for CHF Test Sections
Michael S. Bradbury (Information Systems Laboratory, Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 160-170
Observation of Air Bubble Characteristics by a Vertical Nozzle Under Pool Scrubbing Conditions
Jongwoong Yoon, Yong Hoon Jeong (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 171-180
Thermal-Hydraulic Modeling of Supersonic Steam Injector as a Passive Safety System
Shuichiro Miwa, Nozomu Akiyama (Hokkaido Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 181-190
PIV Measurements Inside a Wire-Wrapped Hexagonal Rod Bundle: From Experiments to Governing Equations
F. Bertocchi, M. Rohde, J. L.Kloosterman (Delft Univ of Technol)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 191-204
A Collaborative Effort Towards the Accurate Prediction of Turbulent Flow and Heat Transfer in Low-Prandtl Number Fluids
A. Shams, F. Roelofs (NRG), I. Tiselj, J. Oder (JSI), Y. Bartosiewicz, M. Duponcheel (UCL), B. Niceno, W. Guo (PSI), E. Stalio, D. Angeli, A. Fregni (UNIMORE), S. Buckingham, L. K. Koloszar, A. V. Ortiz, P. Planquart (VKI), C. Narayanan, D. Lakehal (ASCOMP AG), K. van Tichelen (SCK-CEN), W. Jäger, T. Schaub (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 205-219
Thermal Hydraulic Design of an AcceleratorDriven Subcritical System for Burning Minor Actinides
Adam Kraus, Yan Cao, Elia Merzari, Yousry Gohar (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 220-233
Liquid Metal Thermal Hydraulics?Outcomes of the SESAME Project
F. Roelofs, A. Shams (NRG), A. Batta (KIT), V. Moreau (CRS4), I. Di Piazza (ENEA), A. Gerschenfeld (CEA), P. Planquart (VKI), M. Tarantino (ENEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 234-247
Immortal Experimental Loop at JAEA?Post-Process and Validation
N. Watanabe, H. Obayashi, T. Sugawara, T. Sasa, K. Nishihara (JAEA), D. Castelliti (Belgian Nuclear Research Centre)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 248-261
Steady-State and Transient Experiments in Mock-Up of J-PARC LBE Spallation Target System Using Mockup Loop “IMMORTAL”
H. Obayashi, K.Yamaki, S. Kita, H. Yoshimoto, W. Tao, S. Saito, T. Sasa (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 262-274
The Importance of Phenomena Identification and Ranking Table in Lead Fast Reactor Development
Jun Liao, Richard F. Wright, Paolo Ferroni (Westinghouse), Tanju Sofu (ANL), Sung Jin Lee (Fauske & Associates, LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 275-287
Coupled Calculation of Bubble Departure Diameter and Frequency from Mechanistic Principles for Nucleate Boiling Applications
Marco Colombo, Michael Fairweather (Univ of Leeds)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 288-299
Temperature Distribution Measurement During Quenching of High-Temperature Wall with a Falling Liquid Film
Tomio Okawa, Keisuke Yamagata, Koji Enoki (The Univ of Electo-Communications)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 300-306
Experimental Investigation of Subcooled Flow Boiling and CHF at High Pressure Using High-Resolution Diagnostics
A. Kossolapov, B. Phillips, M. Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 307-318
Enhancement of Pressurized Subcooled Flow Boiling CHF with Nano-Engineered Surfaces
C. Wang, O. Akinsulire, G. Su, B. Phillips, M. Rahman, M. Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 319-328
Uncertainty in Calculations by KWU-MIX of Condensation in the Cold Leg and Downcomer During Pressurized Thermal Shock
Richard R. Trewin (Framatome GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 329-342
How to Bring Conservatism to a BEPU Analysis
Vincent Larget (EdF)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 343-354
Uncertainty Assessment of LOCA Scenario for TRACE Model Based on TRAC-M Input of PWR Reactor
Pawel Domitr, Mateusz Malicki (National Atomic Energy Agency PAA), Lap-Yan Cheng (BNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 355-365
Validation of a BEPU Methodology Through A Blind Benchmark Activity at the PKL Test Facility
J. Freixa, V. Martínez-Quiroga, M. Casamor, F. Reventós (UPC), R. Mendizabal (CSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 366-379
Analysis and Implementation of Design Extension Conditions at Czech NPPs and Contribution (DEC) at Czech NPPS and Contribution of DEC to Enhancement of Defence-in-Depth
P. Kral (UJV)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 380-393
An Artificial Intelligence-Guided Decision Support System for the Nuclear Power Plant Management
Botros Hanna, Tran Cao Son (New Mexico State Univ), Nam Dinh (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 394-406
VIKTORIA Experiments Investigating the Filtering System in the Sump of a PWR After a Loss of Coolant Accident?Part I : Physical/Chemical Effects on Strainer Head Loss Evolution
G. Repetto, B. Migot, J. F. Trigeol (IRSN), V. Soltész (VUEZ as)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 407-420
Using Innovation to Deliver the Nuclear Promise at Exelon
B. Sarikaya, J. J. Tusar, D. S. Knepper, J. McHale, G. Inch, J. R. Massari (Exelon Generation)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 421-425
A Frequency Response Approach to Model Validation for the Compact Integral Effects Test Facility in Transform
Dane De Wet, Per F. Peterson, James C. Kendrick, Christopher Poresky (Univ of California, Berkeley), M. Scott Greenwood (ORNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 426-439
BWR Fuel Bundle Lift Force Measurements, Modeling and Validation
F. Waldemarsson, J.-M. Le Corre, S.-Ö. Lindahl (Westinghouse), U. C. Bergmann, Y. Le Moigne (Westinghouse Electric Sweden AB)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 440-449
Analysis of the Accuracy of Residual Heat Removal in Gen-IV Reactors
Jorge Yanez, Andreas Class (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 450-463
Rod Bundle Post-CHF Heat Transfer Analysis at BWR Prototypical Conditions?Part 2: Heat Transfer Coefficient
J. P. Duarte (Virginia Tech), P. Yarsky T. Zaki (NRC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 464-472
Development of CHF Prediction Method Based on the Film Flow Model with Nucleate Boiling Entrainment
Yuki Narushima, Kenichi Katono (Hitachi)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 473-484
Countercurrent Flows in Vertical Pipes Under Flooding at a Square Top End
Michio Murase, Koji Mishida, Toshiya Takaki (Inst of Nuclear Safety System, Inc.), Raito Goda, Takeyuki Shimamura, Akio Tomiyama (Kobe Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 485-493
Sandia National Laboratories’ Contribution to the OECD/NEA BSAF Phase II Project
N. Andrews, C. Facett, N. Bixler, D. Clayton, R. Gauntt (SNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 494-507
Analysis of Fission Product Transport in Unit 3 of Fukushima Daiichi
L. Fernandez Moguel, T. Lind (PSI), A. Rydl ( INSET s.r.o.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 508-521
Three Weeks Analysis of the Fukushima Daiichi Unit 3 NPP by the SAMPSON Code: Contribution to the BSAF-2 Project
M.Pellegrini, M. Naitoh (IAE)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 522-535
Analysis for the Accident at Unit 3 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project
Jun Ishikawa, Hitoshi Tamaki, Tomoyuki Sugiyama, Yu Maruyama (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 536-547
Computational Experiments to Characterize Bubble Formation and Movement in Waste Glass Foam Layer
Donna P. Guillen, Alexander W. Abboud (INL), Richard Pokorny (UCT Prague)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 548-559
Towards a Two-Phase Flow All-Regime Model for Simulating Transitions from Dispersed to Stratified Regimes
E. V. Kuidjo Kuidjo, M. G. Rodio (CEA), R. Abgrall (Univ of Zürich), P. Sagaut (Aix-Marseille Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 560-573
Interface Tracking Simulations of Bubble Population Effects in PWR Subchannels
Joseph J. Cambareri, Igor A. Bolotnov (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 574-587
Interface Tracking Simulations of Droplet Interaction with Spacer Grids Under DFFB Conditions
Nadish Saini, Igor A. Bolotnov (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 588-600
Assessment of MIT Momentum Closure Relations to Developing, Bubbly Flow Regimes
Brian Casel, Emilio Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 601-614
Importance of Conjugate Heat Transfer Modeling in Transient CFD Simulations
Angel Papukchiev (GRS), Dmitry Grishchenko, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 615-626
CFD Simulation of a Steam Generator U-Bend Region with Anti-Vibration Bars for the Investigation of Local Flow Behavior
D. Vivaldi (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 627-640
A Reduced Order Model Study for Single-Phase Natural Circulation Reactor Stability
Yousef M. Farawila (Farawila et al., Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 641-654
Thermal Hydraulic CFD Validation for Liquid Metal Cooled 19-Pin Hexagonal Wire Wrapped Rod Bundle
A. Batta, A. Class (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 655-665
Study on theTwo-Phase Flow in Simulated LWR Fuel Bundle by CFD Code
Ayako Ono, Susumu Yamashita, Takayuki Suzuki, Hiroyuki Yoshida (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 666-677
Thermal Stratification Analysis in a Pool-Type Geometry
James Schneider, Mark Anderson (Univ of Wisconsin, Madison), Emilio Baglietto, Liangyu Xu (MIT), Zeyun Wu, Sarah Morgan (Virginia Commonwealth Univ), Matthew D. Bucknor, Matthew Weathered (ANL), Sama Bilbao y Leon (OECD NEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 678-687
Experimental Study of Thermal-Hydraulic Performance of a Printed Circuit Heat Exchanger
Keyong Cheng (CAS/Univ of Michigan), Xiulan Huai, Jiangfeng Guo (CAS), Xiaodong Sun (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 688-700
Effect of Indirect Heating of Rod Bundle in Fuel Assembly Thermal Hydraulic Experiment on Local Heat Flux Measurement
Bin Han, Bao-Wen Yang (Delta Energy Group/Xi’an Jiatong Univ), Cen Wei, Yudong Zha (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 701-707
The Effect of Gas-Liquid Properties on Height of Disturbance Waves in a Vertical Annular Two Phase Flow
S. Mori (Kyushu Univ), H. Yoshida (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 708-714
Experimental Investigation on CHF of Water Flowing in Upward Tube from Subcooled to High Qualities
Bing Yang, Minfu Zhao (China Inst of Atomic Energy)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 715-723
The Prospect and Challenge of Nuclear Thermal-Hydraulic Safety Research
Ki-Yong Choi (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 724-737
The U.S. Nuclear Regulatory Commission Approach to Modeling and Simulation of Advanced Non-LWRs: Preparing for the Next Renaissance
Stephen M. Bajorek (NRC), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 738-755
Power-Reactivity Feedback and Oscillations in NuScale Power Module
Yousef M. Farawila (Farawila et al., Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 756-765
Thermal-Hydraulic Stability of the NuScale Reactor Concept
Yousef M. Farawila (Farawila et al., Inc.), Donald R. Todd (Farawila et al., Inc./PNNL), Bryan R. Hayden, Taylor N. Coddington, Hengliang Shen (NuScale Power, L.L.C.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 766-781
Heavy Liquid Metal Thermal Hydraulic Progress in the MYRTE Project
F. Roelofs (NRG), K. Van Tichelen (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 782-795
Inter-Wrapper Flow: LBE Experiments and Simulations
Julio Pacio, Markus Daubner, Thomas Wetzel (KIT), Heleen Uitslag-Doolaard, Akshat Mathur, Ferry Roelofs (NRG)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 796-809
Validation of the System Thermal Hydraulics Code Athlet for the Simulation of Transient Lead-Bismuth Eutectic Flows
Angel Papukchiev (GRS), Clotaire Geffray (CEA), Dmitry Grishchenko, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 810-822
Investigation of the Turbulent Prt Model and Segmentation Rule for LBE Turbulent Heat Transfer
Peiying Li, Yu Hongxing, Li Meifu, Du Sijia, Yan Mingyu, Liu Yu, Zhu Dahuan, Zhang He (Nuclear Power Inst of China)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 823-835
Experimental Investigation of Seismic Vibration on Subcooled Boiling Flow
Yang Zhao, Zhuoran Dang (Purdue Univ), Jingyu Du (Purdue Univ/Tsinghua Univ), Mamoru Ishii (Purdue Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 836-849
Relaxing the Stiffness of Interfacial Friction in the Drift Flux Formulation of Two-Phase Flow
Yousef M. Farawila (Farawila et al Inc.), Daniel Tinkler (Framatome),
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 850-862
Evaluation of Stratified Condensation Models for a Slightly Inclined Tube Using ATHLET Code
Yu Zhang (Deggendorf Inst of Technol/Univ of Luxembourg), Amirhosein Moonesi Shabestary (HZDR/Dresden Univ of Technol), André Bieberle (HZDR), Uwe Hampell (HZDR/Dresden Univ of Technol) Stephan Leyer (Univ of Luxembourg)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 863-875
High-Fidelity Simulations of Boiling
Akash Dhruv, Elias Balaras (George Washington Univ), Amir Riaz, Jungho Kim (Univ of Maryland)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 876-887
Preliminary Analysis of Measured Data from a Simulated BWR Fuel Assembly Undergoing Power and Flow Oscillations Representative of Anticipated Transient Without SCRAM Conditions
P. Yarsky, T. Zaki (NRC), J. P. Duarte (VT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 888-901
The Effect of Reactor Control Systems on BWR Stability Using Unique Plant Data
Carl Adamsson (Vattenfall Nuclear Fuel AB), David Palko, Thomas Smed (Forsmark Kraftgrupp AB)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 902-909
VIKTORIA Experiments Investigating the Filtering System in the Sump of a PWR After a Loss of Coolant Accident?Part II: Downstream Effects
G.Repetto, B. Migot, C. Heib (IRSN), V. Soltész (VUEZ as)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 910-923
A Methodology for Predicting the Fouling of Steam Generators and Its Impact on Their Performance
Thibaut Dupuy, Thomas Prusek, Fadila Oukacine (EdF), Marc Jaeger (Univ of Aix-Marseille), Marcel Lacroix (Univ of Sherbrooke)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 924-937
Modification of 37-Element Fuel Bundle for Recovering Thermal Margin
J. H. Park, J. Y. Jung (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 938-944
Develop of Calculation-Analytical Justification of Possibility of Increasing the Thermal Power of Reactor for Unit 4 of Rivne NPP to 101.5% Nnom. (up to 3045 MW)
Oleksandr Mykhailenko, Oleksandr Mazurok, Vadym Ivanov (ESG Group), Yuriy Hubenya (SD Rivne NPP)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 945-955
Advanced Studies and Statistical Treatment for Sodium-Cooled Fast Reactor PIN Failures During Unprotected Transient Overpower Accident
N. Marie (CEA), K. Herbreteau, A. Marrel, F. Bertrand (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 956-969
Benchmarking of RAMONA5-FA to Oskarshamn-2 Instability Event
Daniel R. Tinkler, Cameron D. Myers (Framatome), Yousef M. Farawila (Farawila et al Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 970-980
Assessment of Smoothed Particle Hydrodynamics Methods for Simulating the External-Flooding Scenario
L. Lin, Nam Dinh (NCSU), S. Prescott, H. Bao (INL), N. Montanari, R. Sampath (Centroid Lab)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 981-992
Uncertainty and Sensitivity Analysis of PSBT with ATHAS Subchannel Code
Peichao Zhai, Bo Zhang, Jianqiang Shan (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 993-1005
Rod Bundle Post-CHF Heat Transfer Analysis at BWR Prototypical Conditions?Part 1: Inverse Heat Transfer
J. P. Duarte (Virginia Tech), P. Yarsky, T. Zaki (NRC), M. L. Corradini (Univ of Wisconsin, Madison)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1006-1016
Steady-State Flow CHFs with Various Tube Materials
Soon Kyu Lee (Univ of New Mexico), Nicholas R. Brown (Univ of Tennesseee, Knoxville), Kurt A. Terrani (ORNL), Youho Lee (Seoul National Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1017-1022
Initial Entrained Fraction at Onset of Annular Flow
Henryk Anglart (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1023-1034
Findings on Fukushima Daiichi NPP Severe Accident and Implication to SA Code Validation
Shinya Mizokami (Tokyo Electric Power Co.), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1035-1047
Best Practices for CFD Grade Experiments and Recent Developments in High-Resolution Measurement Techniques
Annalisa Manera, Victor Petrov (Univ of Michigan), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1048-1060
Liquid Metal Thermal Hydraulics: State-of-the-Art and Future Perspectives
F. Roelofs (NRG), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1061-1074
Scaling Analysis of Thermal-Hydraulic Integral Systems: Insights from Practical Applications and Recent Advancements
C. Frepoli (FPoliSolutions LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1075-1079
On Numerical Simulation of Flashing Flows
Yixiang Liao, Dirk Lucas (HZDR)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1080-1092
Preliminary Development of a Coarse-Mesh Sodium Boiling Model for OpenFOAM Based Mult-Physics Solvers
Stefan Radman, Carlo Fiorina, Andreas Pautz (EPFL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1093-1106
Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase II?Results of Severe Accident Analyses for Unit 1
L. E. Herranz (CIEMAT), Marco Pellegrini (IAE), T. Lind (PSI), M. Sonnenkalb (GRS), L. Godin-Jacqmin (CEA), C. López (CIEMET), K. Dolganov (IBRAE), F. Cousin (IRSN), H. Tamaki (JAEA), T. W. Kim (KAERI), H. Hoshi (NRA), N. Andrews (SNL), T. Sevon (VTT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1107-1118
Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2?Results of Severe Accident Analyses for Unit 2
M. Sonnenkalb (GRS), M. Pellegrini (IAE), L. E. Herranz (CIEMAT), T. Lind (PSI), A. C. Morreale (CNL), J. Kanda (CRIEPI), H. Tamaki (JAEA), S. I. Kim (KAERI), F. Cousin (IRSN), L. Fernandez Moguel (CIEMAT), N. Andrew (SNL), T. Sevon (VTT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1119-1132
Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2?Results of Severe Accident Analyses for Unit 3
T. Lind (PSI), M. Pellegrini (IAE), L. E. Herranz (CIEMAT), M. Sonnenkalb (GRS), Y. Nishi (CRIEPI), H. Tamaki (JAEA), F. Cousin (IRSN), L. Fernandez-Moguel (PSI), N. Andrews (SNL), T. Sevon (VTT T)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1133-1146
Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project
M. Pellegrini (IAE), L. E. Herranz (CIEMAT), M. Sonnenkalb (GRS), T. Lind (PSI), Y. Maruyama (JAEA), R. Gauntt, N. Bixler (SNL), A. Morreale (CNL), K. Dolganov (IBRAE), T. Sevon (VTT), D. Jacquemain (IRSN), J. H. Song (KAERI), H. Hoshi (NRA), Y. Nishi (CRIEPI), S. Mizokami (TEPCO)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1147-1162
Direct Numerical Simulations of Low-Prandtl Turbulent Heat Transfer in Planar Impinging Jets
M. Duponcheel, Y. Bartosiewicz (Universite Catholique de Louvain)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1163-1176
A Parameterized Proper Orthogonal Decomposition Approach for Reduced Order Models
T. P. Grunloh, L. Calian (Univ of Illinois), S. Natesh, A. Patel, T. Wilson (Illinois Rocstar LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1177-1190
CFD Simulation of Condensation Heat Transfer in Horizontal Tubes
Khalid Khasawneh, Yong Hoon Jeong (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1191-1204
Numerical Simulation on Fuel Assembly Deformation Induced by Flow Redistribution with Code_SATURNE
T. Xu, J. X. Han, J. Min (EDF China Center), M.-C. Gauffre, R. Denefle (EDF)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1205-1217
Les Investigation of Prandtl Number Effects over a Backward Facing Step and Consequences in Terms of Best Practice Guidelines for RANS
S. Buckingham, L.Koloszar, A. Villa Ortiz (von Karman Inst for Fluid Dynamics), Y. Bartosiewicz, G. Winckelmans (UCLouvain)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1218-1231
Numerical Simulation on LMR Molten-Core Centralized Sloshing Behaviors with Single/Multi-Phase Smoothed Particle Hydrodynamics Based on Novel Density Formulation
Young Beom Jo, Eung Soo Kim (Seoul Natl Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1232-1245
A 3D Model to Solve U-Tube Steam Generator Secondary Side Thermal Hydraulics with Coupled Primary-to-Secondary Side Heat Transfer
D. Vivaldi (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1246-1259
Development and Implementation of a 1-D FEM Compressible Flow Module in TRICORDER?A MOOSE-Based Multi-Physics Code
L. B. Carasik, V. Patel, S. Judd, P. Venneri (UNSC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1260-1274
Experimental Study of Gas-Liquid Two-Phase Flow Behavior with Steam Condensation During Pool Scrubbing
Yuki Nakamura, Kota Fujiwara, Akiko Kaneko, Yutaka Abe (Univ of Tsukuba)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1275-1287
A New Dataset with Local Measurement and Visualization of Subcooled Boiling in an Internally Heated Annulus Channel
Joseph L. Bottini (Univ of Illinois), Longxiang Zhu, Zhiee Jhia Ooi, Taiyang Zhang, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1288-1298
Relative Motion Between Phases in Horizontal Gas Dispersed Flow
Ran Kong (Purdue Univ), Jiawei Bian (Purdue Univ/Xi’an Jiao Tong Univ), Qingzi Zhu, Mamoru Ishii, Seungjin Kim (Purdue Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1299-1312
Experimental Study of Liquid Entrainment in ADS-4 Branch Tube with Double-End Inlets of Air-Water
Liu Wang (Xi’an Jiaotong Univ), Lifang Liu (State Power Investment Corp. Research Inst), Ning Wang (Xi’an Jiaotong Univ), Qionghua Sun (State Power Investment Corp. Research Inst) , Kui Zhang (Xi’an Jiaotong Univ), Xiaoliang Fu (State Power Investment Corp. Research Inst) , Wenxi Tian (Xi’an Jiaotong Univ), Bo Dong (State Power Investment Corp. Research Inst), Suizheng Qiu, G. H. Su (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1313-1322
Printed Circuit Heat Pipe Heat Exchanger for Passive Containment Cooling System
Hae-Yong Jeong (Sejong Univ), In-Sik Ra (Energy Hub)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1323-1331
PANAS- Project: Heat Transfer Model Development for Passive Safety Systems
Stephan Leyer (Deggendorf Inst of Technol/Univ of Luxembourg), Uwe Hampel (HDZR/Dresden Univ of Technol), Christoph Schuster, Wolfgang Lippmann (Dresden Univ of Technol), Markus Walther (Framatome GmbH), Kai Kosowski (PreussenElektra GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1332-1345
Fouling Effect of Lead Oxide Crystallization on Heat Transfer in LBE
Yong-Hoon Shin, Kristof Gladinez, Jun Lim, Alessandro Marino, Kris Rosseel, Alexander Aerts, Katrien Van Tichelen (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1346-1359
Development of a Numerical Framework to Model Flow Accelerated Corrosion in a Lead Loop
Khaled Talaat, Rubel Das, Brian Romero, Cemal Cakez, Osman Anderoglu, Sang Lee (Univ of New Mexico), Youho Lee (Seoul Natl Univ), Heng Ban (Univ of Pittsburgh), Keith Woloshun, Seung Jun Kim, Dasari Rao, Cetin Unal (LANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1360-1370
Image Analysis of Bubbling Mode Condensation Oscillations in Horizontal Sparger
Elina Hujala, Vesa Tanskanen, Giteshkumar Patel, Juhani Hyvärinen (Lappeenranta-Lahti Univ of Technol)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1371-1382
A Potential Solution for Boiling Crisis
Prem Bikkina, Sushobhan Pradhan (Oklahoma State Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1383-1396
Critical Heat Flux in Vertical Annulus Under Zero Flow Conditions with Radial Heat Losses
Lior Nahon (NRCN/Ben-GurionUniv), Tali Bar-Kohany (NRCN/Tel Aviv Univ), Evgeny Rabinovich (NRCN), Yosef Aharon (NRCN/Ben Gurion Univ
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1397-1404
Current Capability of Interfacial Area Transport Equation in Subcooled Boiling
Longxiang Zhu (Univ of Illinois/Xi’an Jiaotong Univ), Zhiee Jhia Ooi, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1405-1415
Integral Effect Tests in Visualization Basis 3D Printed Test Facility for Improved Applicability of Innovative Technologies
Kyung Mo Kim, In Cheol Bang (UNIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1416-1426
Development of Operation Strategy and Recovery Guideline During Extended Station Blackout for OPR1000 and APR1400
Chang Gyun Lee, Jae Min Park, Ho Bin Yim, Chan Eok Park, Gyu Cheon Lee (KEPCO E&C)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1427-1437
Thermal-Hydraulic Calculations and Development of Boundary Conditions for Assessing the Technical Condition and Life Time Extension of Primary Main Equipment for Reactor Facility KHNPP-1
Oleksandr Mykhailenko, Oleksandr Mazurok, Vadym Ivanov (ESG Group)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1438-1451
Feasibility Study of TES Integrated Nuclear Power Plant
Ju Yeon Lee, Jeong-Ik Lee (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1452-1461
Two-Fluid Equation Considering Time-Dependent Change of Fluid Volume
Jong Hyuk Lee, Kyung Doo Kim (KAERI), Byoung Jae Kim (Chungnam National Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1462-1472
Establishment of Guideline for Credibility Assessment of Nuclear Simulations in the Atomic Energy Society of Japan
Masaaki Tanaka (JAEA), Yoshiro Kudo (CRIEPI), Kotaro Nakada (Toshiba Energy Systems and Solutions Corp.), Seiichi Koshizuka (Univ of Tokyo)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1473-1484
Development of a One-Dimensional Model for a Closed Thermosiphon for Cooling a Spent-Fuel Pool
Richard R. Trewin (Framatome GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1485-1497
Development of Nuscale Critical Flux Correlations
A. Galimov (NuScale Power LLC), M. Bradbury (Information Systems Laboratories, Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1498-1508
Modeling and Validation of a Post-Dryout Heat Transfer Model for Three-Field Sub-Channel Analysis
J.-M. Le Corre (Westinghouse Electric Sweden AB)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1509-1527
Experimental Research of Critical Heat Fluxes on 37-Rod Bundles with Various Types of Intensifying Grids
D. Oleksyuk, D. Kireeva, L. Kobzar (NRC “Kurchatov Inst”)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1528-1541
Validation of Cathare 3D Module on LSTF Core
Raphaël Préa (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1542-1554
High-Fidelity Simulation of a Taylor Bubble in Co-Current Turbulent Flow
B.Mikuz (NRG/Jozef Stefan Inst), E. M. A. Frederix (NRG), I. Tiselj (Jozef Stefan Inst), E. M. J. Komen (NRG)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1555-1568
Benchmarking of CFD Modelling Closures for Two-Phase Turbulent Bubbly Flows
Marco Colombo (Univ of Leeds), Roland Rzehak (HZDR),Michael Fairweather (Univ of Leeds), Yixiang Liao, Dirk Lucas (HZDR)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1569-1582
CFD Simulations of Direct-Contact Condensation of Horizontal Vapor Jets
T. Pättikangas, J. Peltola, V. Hovi (VTT Technical Research Centre of Finland Ltd), M. Puustinen, A. Räsänen, E. Kotro (Lappeenranta-Lahti Univ of Technol)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1583-1596
An Eulerian-Eulerian CFD Approach to Simulate the Themohydraulics of Pipes; Channels or Rod Bundles: From Onset of Nucleate Boiling to CHF
Wei Ding (HZDR/TU Dresden), Eckhard Krepper (HZDR), Uwe Hampel (HZDR/TU Dresden)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1597-1607
Uncertainty Analysis of Corium Relocation to the Lower Plenum Using Results from the OECD/NEA BSAF Phase II Project
Lucas I. Albright, Nathan Andrews, Larry Humphries, Randall O. Gauntt (SNL), Tatjana Jevremovic (Univ of Utah)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1608-1621
Reconstruction of the Fukushima Source Term from Nearby Radiological Measurements
Martin Sogalla, Martin Sonnenkalb, Sebastian Band, Cornelia Richter (GRS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1622-1635
Analyses of Fission Products Behaviour and Environmental Releases During the Fukushima-Daiichi Accident by Direct and Inverse Approach at IRSN
Frédéric Cousin, Hervé Bonneville Charlaine Bouillet, Damien Didier, Didier Jacquemain (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1636-1649
Outline of the OECD/NEA/ARC-F Project
Toru Nakatsuka, Toshikatsu Maeda, Tomoyuki Sugiyama, Yu Maruyama (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1650-1656
A Novel Coarse-Grid Sub-Channel CFD for Nuclear Thermal Hydraulics
B. Liu, S. He (Univ of Sheffield), C. Moulinec (Science and Technology Facilities Council), J. Uribe (EDF Energy R&D UK Center)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1657-1670
CFD Studies of Effect of Fuel Channel/Stringer Eccentricity in the Core of an Advanced Gas-Cooled Reactor
Jundi He, Shuisheng He (Univ of Sheffield), Bing Xu (EDF Energy)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1671-1684
CFD Analysis on Mixing Vane Grid Performance in a 5x5 Rod Bundle
Bin Han, Bao-Wen Yang (Delta Energy Group/Ji’an Jiaotong Univ), Cen Wei, Yudong Zha (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1685-1697
Reynolds-Averaged Turbulence Modeling Using Deep Learning with Local Flow Features
Chih-Wei Chang (Emory Univ), Jun Fang (ANL), Nam T. Dinh (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1698-1711
Numerical Simulation of Nonlinear Bubble Phenomena in Subcooled Boiling in a Channel
Jyoti Bhati, Swapan Paruya, J. Naik, L. G. Mayur, B. Das (NIT Durgapur), Subhramaniam Pushpavanam (ITT Madras)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1712-1725
CFD-DEM Analysis of Realistically Heated Pebble Bed Geometry
Robert Mardus-Hall. Guan Heng Yeoh (Univ of New South Wales), Mark Ho (ANSTO)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1726-1739
Hypothetical Accident Analyses on the Conceptual NIST Reactor with a Split Core Using RELAP5-3D
Tao Liu, Zeyun Wu (Virginia Commonwealth Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1740-1749
Investigation of Liquid Film Behavior in Upper Reactor Vessel Downcomer with Electrical Conductance Sensor Based on Flexible Printed Circuit Board
Chi-Jin Choi, Hyoung Kyu Cho (Seoul Natl Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1750-1761
That Dam Quality
Jeff Fluckiger, Daren Jensen (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1762-1771
Experiments on Helium-3 Negative Reactivity Insertion -HENRI- Prototype
G. Mignot, A. Warren, S. Balderrama, W. Marcum (OSU), N.Woolstenhulme (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1772-1783
Research Progress of Fission Gas Separation Technology Applied in Thorium Molten Salt Reactor
Junlian Yin, Tingting Zhang, Yalan Qian, Dezhong Wang (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1784-1793
System Thermal-Hydraulics During SBO with a Passive Safety Feature of Hybrid SIT
Seok Cho, Byoung-Uhn Bae, Jae-Bong Lee, Yu-Sun Park, Jong-Rok Kim, Kyoung-Ho Kang (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1794-1804
BEPU of MSLB LOCA on a Generation III Reactor Based on RELAP5/SCDAP 3.4
Ye Yang, Jun Yang, Chengcheng Deng (Huazhong Univ), Mamaru Ishii (Purdue Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1805-1825
Results on Thermal Hydraulic Experiments in the LBE-Cooled Scaled Pool Facility E-SCAPE in Support of the Myrrha Design and Licensing
Katrien Van Tichelen, Fabio Mirelli (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1826-1836
LBE-Cooled Scaled Pool Facility E-SCAPE: Results and Applications for Code Validation
D. Castelliti, K.Van Tichelen, F. Mirelli (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1837-1850
Validation of CFD Analyses Against Pool Experiments E-SCAPE
D. C. Visser, F. Roelofs (NRG), F. Mirelli, K. Van Tichelen (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1851-1861
Numerical Simulation of Loss-of-FlowTransient in the MYRRHA Reactor
L. Koloszar, Ph.Planquart (Karman Inst for Fluid Dynamics), K Van Tichelen, S. Keijers (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1862-1875
A Preliminary Study On Biphilic Surface for Enhanced Pool Boiling Performance
Do Yeong Lim, In Cheol Bang (UNIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1876-1881
Modelling Path of the Heterogeneous Spontaneous Nucleation?A New Driven Mechanism of Power Transient CHF
Yikuan Yan, Emory Brown, Wade Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1882-1892
An Experimental Study of Steam Condensation with the Presence of Air Under Free Convection Condition
Jinhoon Kang, Byongjo Yun (Pusan National Univ), Sang-Gyu Lim, Jong Cheon (KHNP Central Research Inst)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1893-1906
Boiling Heat Transfer Enhancement with Extremely High Thermal Effusivity of Phase Change Material
Ji Yong Kim, In Cheol Bang (UNIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1907-1916
EDF MAAP5.04 LOCA Transient Simulations Improvements
Jeremy Bittan (EdF)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1917-1930
Uncertainty Analysis of Severe Accident in the Spent Fuel Pool
V. Vileiniskis, A. Kaliatka, E. Ušpuras (Lithuanian Energy Inst), D. Merrouche (CRNB)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1931-1943
Uncertainty Analysis of Vessel Failure Mode and Melt Release in Station Blackout Scenario in Nordic BWR Using MELCOR Code
Sergey Galushin, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1944-1956
The Effect of Severe Accident Scenarios on In-Vessel Debris Relocation in Nordic BWRs
Sergey Galushin, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1957-1970
Status of TRACE Model Development and Validation at NPP Gösgen in Switzerland
Davide Papini, Rainer Kaulbarsch, Jens-Uwe Klügel (Nuclear Power Plant Gösgen-Däniken AG), Evgeni Borisov, Kaliopa Mancheva (GCR Ltd)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1971-1984
Applicability of the TRACE Model of NPP Gösgen to Safety Analyses of BDBA Sequences
Davide Papini, Rainer Kaulbarsch, Jens-Uwe Klügel (Nuclear Power Plant Gösgen-Däniken AG), Evgeni Borisov, Kaliopa Mancheva (GCR Ltd.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1985-1997
Thermal-Hydraulic Calculations for Technical Condition and Llifetime Extension Assessment of SUNPP-3 Reactor
Oleksandr Mazurok, Oleksandr Mihaylenko (ESG), Volodymyr Kravchenko (Odessa National Polytechnic Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1998-2011
Determination of Representative Validation Scenarios for Emergency Operating Guidelines
Qingming Yang (China Nuclear Power Eng Co., Ltd.), Minfeng Chen (China Zhongyuan Eng Corp.), Jun Wang (China Nuclear Power Eng Co., Ltd)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2012-2022
Validation of Numerical Particle Tracking Inside a HLM Reactor with Measurements in a Water Model
Ph. Planquart, C. Spaccapaniccia, S. Buckingham (von Karman Inst), K. Van Tichelen (SCK-CEN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2023-2035
Validation of NEK5000 for 37- and 61-Pin Wire-Wrap Geometries with Conjugate Heat Transfer
Aleksandr Obabko, Elia Merzari (ANL), Landon Brockmeyer (Texas A&M), Paul Fischer (ANL/Univ of Illinois), Tanju Sofu (ANL), Brian Jackson, Michael Steer (TerraPower), Rodolfo Vaghetto, Yassin A. Hassan (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2036-2049
CFD Verification and Validation of Wire-Wrapped Pin Assemblies
Mathieu Martin, Daniel Leonard, R. Brian Jackson, K. Michael Steer (TerraPower)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2050-2063
Toward Exascale: Large Eddy Simulation and Direct Numerical Simulation of Nuclear Reactor Flows with the Spectral Element Method
Elia Merzari (ANL), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2064-2080
Separate-Effect Experiments and Modeling for Two-Phase Flow Under Geometric Restrictions
Seungjin Kim, Ran Kong (Purdue Univ), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2081-2094
Development of a Fast Reactor and Related Thermal Hydraulics Studies in Japan
Hiroyuki Ohshima, Hideki Kamide (JAEA), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2095-2107
Overview of Mitigation Models Dedicated to Severe Accidents and Consequences on Flow Rate Through Containment Concrete Structures
Stephane Mimouni (EdF R&D), Paul Baconnier (ESPCI), Germain Day (EdF R&D)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2108-2122
Development and Multi-Level Validation of a Mechanistic Heat Flux Partitioning Model for Boiling Heat Transfer
Ravikishore Kommajosyula, Etienne Demarly, Emilio Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2123-2136
Numerical Simulation of Film Boiling on a Horizontal Surface in Oscillating System
Young Seock An, Byeongjae Jae Kim, Nam Kyu Ryu (Chungnam National Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2137-2148
On Development and Validation of Subcooled Nucleate Boiling Models for OpenFOAM Foundation Release
J. Peltola, T. Pättikangas (VTT Technical Research Centre of Finland Ltd), W. Bainbridge (CFD Direct Ltd), R. Lehnigk, F. Schlegel (HZDR)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2149-2163
Design and CFD Modeling of the Gas Injection System for the Out-of-Pile HENRI Facility
S. Balderrama Prieto, G. Mignot, W. Marcum (OSU), N. Woolstenhulme (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2164-2176
Study of Transient CHF and Post-CHF Flow Boiling
Soon Kyu Lee (Univ of New Mexico), Nicholas R. Brown (Univ of Tennessee,-Knoxville), Kurt A. Terrani (ORNL), Colby B. Jensen (INL), Heng Ban (Univ of Pittsburgh), Youho Lee (Seoul National Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2177-2182
A Systematic Approach to Inform Experiment Design Through Modern Modeling and Simulation Methods
A. Epiney, C. Rabiti, C. Davis (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2183-2196
Sensitivity Studies of Heater Rod Design for Transient Critical Heat Flux Experiments In TREAT
Richard O. Hernandez (Penn State), Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen (INL), Jacob P. Gorton, Nicholas R. Brown (Univ of Tennesse, Knoxville)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2197-2208
Comparison of Computational Fluid Dynamics and Subchannel Numerical Solutions of Fuel Assemblies Characterised by Bowing
R. Puragliesi, R. Mukin, I. Clifford, H. Ferroukhi (PSI), M. Seidl (PreussenElektra GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2209-2222
Development of a Data-Driven Turbulence Model for 3D Thermal Stratification Simulation During Reactor Transients
Yangmo Zhu, Nam Dinh (NCSU), Rui Hu, Adam Kraus (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2223-2234
Parametric Evaluation of Thermal Performance of Concentric Recuperator Heat Exchanger for Multifunctional Forced Convection PBLI LOOP DRAGON-V
Muhammad Salman Khan (CAS/Univ of Science and Technol of China), Qunying Huang, Yunqing Bai, Lei Wang, Zhiqiang Zhu (CAS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2235-2245
Development and Assessment of Adjoint Sensitivity Analysis Method for Transient Two-Phase Flow Simulations
G. Hu (ANL/Univ of Illinois), T. Kozlowski (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2246-2259
Comparison of the 3D Nodal Integral Method for Arbitrary Hexahedral Elements and Spectral Element Method
Ibrahim Jarrah, Rizwan- Uddin (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2260-2273
Critical Flow Prediction by System Codes?Recent Analyses Made Within the FONESYS Network
M. Lanfredini (GRNSPG-UNIPI), D. Bestion (Consultant), F. D’Auria, N. Aksan (GRNSPG-UNPI), P. Fillion (CEA), P. Gaillard (Framatome), J. Heo (KAERI), I. Karppinen (VTT), K. D. Kim (KAERI), J. Kurki, L. Lifang, A. Shen (SPICRI), J.-L. Vacher (EdF), D. Wang (CNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2274-2287
Simulation and Analysis of the Sodium-Cooled Fast Reactor Steam Generator
Zenan Che, Peng Du, Bo Zhang, Pan Wu, Li Ge, Jianqiang Shan, Junli Gou (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2288-2301
Experimental Study of the Surface Evaporation Rate of a Heated Water Pool Using Infrared Thermography
J. Martin, B. Migot (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2302-2313
Quenching Experiment of Cr-Alloy Accident Tolerant Cladding Under Low and High Subcooling Conditions
Wang Kee In, Kwan-Geun Lee (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2314-2323
Velocity- and Scalar-Field Measurements of Turbulent Buoyant Jets in a Two-Layer Stratified Environment
Sunming Qin, Victor Petrov, Annalisa Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2324-2337
Intelligent Identification System for Boiling Dynamics from Acoustic Emission Signal Using Machine Learning Technique
Seok Bin Seo, Do Yeong, Lim, In Cheol Bang (UNIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2338-2349
Prospects for a CEA and ROSATOM/IPPE Collaborative Program on Na Boiling for GEN IV SFRs Safety: Rationale and Thermal-Hydraulic Preparatory Work
M. Anderhuber, A. Gerschenfeld, Y. Gorsse, N. Alpy C. Latge, J. Perez-Manes (CEA), Yu. Kuzina, A. Sorokin, I. Berensky, A. Volkov, Yu. Chernukhina, K. Raskach (IPPE)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2350-2363
Comparison of Margins of Sodium Bulk Boiling and Reactor Vessel Creep Under RVACS Operation by Micro-Integral Effect Test
Minho Lee, In Cheol Bang (UNIST), Dong-Wook Jerng (Chung-Ang Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2364-2376
Fragmentation Behavior and Heat Transfer During Molten Aluminum-Liquid Sodium Interaction
Liang Hu, Kui Ge, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2377-2383
Calculation Tool for Heat Exchanger Tube Rupture in Pool-Type Reactors
D. Castelliti (SCK-CEN), G. Lomonaco (GeNERG – DIME/TEC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2384-2397
Experimental Campaign in Support of the Safety Studies of the STGR in LFR
Alessandro Del Nevo, Marcia Eboli (ENEA), Alessio Pesetti, Nicola Forgione (Univ of Pisa)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2398-2410
Characterization of Leak Detection in HLM System Using LIFUS5/MOD3 Facility
Marica Eboli, Alessandro Del Nevo (ENEA), Nicola Forgione (Univ of Pisa), Fabio Giannetti (Sapienza Univ of Rome), Daniele Mazzi (SRS S.r.l.), Marco Ramacciotti (ISE S.r.l.),
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2411-2424
Numerical Analysis of the Axial Lead-Bismuth Pump Performace Base on the Different Rotation Speed
Kailin Wang, Liangxing Li, Wei Xie, Shuangbao Zhang (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2425-2438
Infrared Study of Flow Boiling and CHF on Prototypical Surfaces with Nuclear Fuel Cladding Morphology
Guan-Yu Su, Chi Wang, Jee Hyun Seong, Artyom Kossolapov, Bren Phillips, Matteo Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2439-2446
Enhancement of Condensation Heat Transfer by Hydrophobic and Nano Porous Surface
Taeseok Kim, Yun Sik Cho, Sung Joong Kim (Hanyang Univ), Jaemin Lee, Wonjoon Choi (Korea Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2447-2460
Dependence of Nanoscale Roughness on Wicking-Based CHF Enhancement for Fresh and Oxidized Cr-Coated Surfaces
Namgook Kim, Hong Hyun Son, Sung Joong Kim (Hanyang Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2461-2469
Direct Contact Condensation Induced Transition from Oscillatory Bubble to Stratified Flow
Dingding Liang, Lu Tao, (Beijing Univ of Chemical Technol)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2470-2482
Simplified Thermohydraulic Criteria for a Comparison of the Accidental Behaviour of Gen-IV Nuclear Reactors and of PWRS
F. Bertrand, N. Marie, A. Bachrata, J. B. Droin, X. Manchon (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2483-2496
Analyses with MELCOR Code of an Unmitigated SBO Scenario with In Vessel Retention Strategy Applied to a Generic PWR 900 MWe
F. Mascari, S. Ederli (ENEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2497-2510
Pressurized Environments and Effect of Silica Gel Amount on Depressurization Inside the Containment
Dong Hoon Kam, Yong Hoon Jeong (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2511-2518
Development of Risk Oriented Accident Analysis Methodology (ROAAM+) for Assessment of Ex-Vessel Severe Accident Management Effectiveness
P. Kudinov, S. Galushin, D. Grishchenko (KTH), S. Yakush (IPMech RAS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2519-2535
Screening Analysis for Pressurized Thermal Shock (PTS) Transient Scenarios
R. Mukin, I. Clifford, O. Costa Garrido, D. F. Mora, M. Niffenegger, B. Niceno, H. Ferroukhi (PSI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2536-2549
RELAP5-3D Simulation of Complex Flow Patterns Both In-Core and Inside the Reactor Upper Plenum to Assess the Performance of Reactor Coolant Temperature Sensors Located at the Core Outlet and In-Core Eletations
Alex Matev (BEL V)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2550-2563
Thermal Analysis for the Spent Fuel Pool Integrated with the Reactor Cavity of the Chinshan Plant Using GOTHIC
Yen-Shu Chen, Li-Ying Huang, Lin Ansheng, Yng-Ruey Yuann (INER)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2564-2576
Experimental Study of an Adiabatic Two-Phase Flow in a Simulated PWR Spent Fuel Bundle
G. Brillant, J. Martin, B. Fourré (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2577-2586
Containment Spray Experiments in MISTRA Facility for Heat and Mass Transfer Model Validation in Superheated Atmosphere
C. Ghitiu, E. Demay (EdF SA), E. Studer, D. Abdo, P. Debesse, B. Cariteau, G. Bernard-Michel, F. Dabbene (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2587-2600
Experimental Investigations on the Heat Transfer Characteristics of Supercritical CO2 in a Single Circular Tube with Direct Electrical Heating
Konstantinos Theologou, Rainer Mertz, Jörg Starflinger (Univ of Stuttgart)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2601-2614
Experimental Investigation of Heat Transfer Characteristics in Tubes to Cool CO2 Near the Critical Point in Horizontal Flow Orientation
Andreas Wahl, Rainer Mertz, Jörg Starfliner (Univ of Stuttgart)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2615-2628
Validation of CFD Application Scheme on the Critical Heat Flux Phenomena in Rod Bundle Channel with Spacer Grids
Xiaomeng Dong, Zhijian Zhang, Zhaofei Tian, Guangliang Chen (Harbin Eng Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2629-2639
CFD Modeling and Sensitivity Analysis of Ex-Vessel Core Melt Process
Pavel Zacha, Vaclav Zenezny (CTU in Prague, FME)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2640-2651
RANS Simulations of Turbulent Round Jets in the Presence of Density Difference and Comparison with High-Resolution Experimental Data
Jiaxin Mao, Sunming Qin, Victor Petrov, Annalisa Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2652-2665
Development and Validation of a Conjugate Heat Transfer Model for the Two-Phase CFD Code NEK-2P
Prasad Vegendla, Adrian Tentner, Dillon Shaver, Aleks Obabko, Elia Merzari (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2666-2685
Analysis of Wall Nucleation Modeling for Flow Boiling in Fluent
Longcong Wang, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2686-2698
Development of Thermal Hydraulic Simulation Method for Two-Phase Flow in Steam Generators
Yoshiteru Komuro, Atsushi Kodama, Ling Cheng, Yoshiyuki Kondo, Seinosuke Azuma, Hideyuki Morita,Koichi Tanimoto, Ryoichi Kawakami, Toshifumi Nariai (MHI), Yoshito Nishikawa (The Kansai Electric Power Co., Inc.), Takashi Hibiki (Purdue Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2699-2712
A Subcooled Boiling Model Developed for Narrow Rectangular Channels Based on the CFD Method
Linfeng Li, Mingjun Wang, Dalin Zhang, Wenxi Tian, G.` S. Su, Suizheng Qiu (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2713-2725
Experimental Design for Transient in-Pile Boiling Studies at the TREAT Facility
Colby Jensen, Nicolas Woolstenhulme, Charles Folsom, David Kamerman, Austin Fleming, Daniel Wachs (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2726-2737
Thermal Design of the TREAT Facility
Bradley Heath, Colby Jensen (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2738-2749
Visual Inspection to Monitor / Detect Boiling
Colby B. Jensen (INL), Kevin Terrill, Alberto Cardenas, Richard Christensen (Univ of Idaho)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2750-2761
Comparison of Integration Methods of STAR-CCM+ and RELAP5-3D for Application to Sodium Based on TREAT Experiments
Cole Blakely (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2762-2771
Optimization of Heat Transfer Rate Around Cylindrical PCM Containers in Energy Storage Coupled with Nuclear Power Plant
Ahmed K. Alkaabi, Yacine Addad, Saeed A. Alameri (Khalifa Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2772-2780
A Parametric CFD Boiling Study Using State-of-the-Art Two-Phase and Boiling Closure Models
Junsoo Yoo (INL), Emilio Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2781-2794
Accuracy Analysis of Near Wall Thermal Hydraulics Modeling of Molten Salt Reactors
M. Tano, Pablo Rubiolo (Univ of Grenoble-Alpes), Jean Ragusa (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2795-2808
An Advanced Ultrasonic Waveguide Concept for Spatially Distributed Monitoring of In-Core Temperatures
N. O. Cetiner, S. M. Cetiner, M. J. Roberts, V. K. Varma, G. Muralidharan, T. R. Muth, R. A. Montogomery (ORNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2809-2817
Experimental Investigation on the Double-Hole Steam Jets Condensation Characteristics
Yuhao Zhang, Yonglong Yuan, (NCEPU), Lifang Liu, Xiaoliang Fu (SPIC/National Energy Key Laboratory of Nuclear Power Software), Li Feng (NCEPU), Zhongyi Wang (SPIC/National Energy Key Laboratory of Nuclear Power Software), Daogang Lu (NCEPU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2818-2825
Experimental Study on Single-Phase Flow Resistance Characteristics of Rectangular Channels with Lateral Non-Uniform Heating
Rulei Sun, D. L. Zhang, Jiancheng Zhou, Gongle Song, Wenxi Tian, Suizheng Qiu, G. H. Su (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2826-2839
Development of a Serpentine Tube Type Steam Generator with an Intermediate Heat Transfer Fluid for Prevention of SWR
Hyungmo Kim, Jung Yoon, Jaehyuk Eoh (KAERI), Namhyeong Kim, Moo-Hwan Kim (POSTECH), Dong Eok Kim (CAU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2840-2849
Natural Convection of a Droplet-Laden Flow in a Cylindrical Enclosure Above a Hot Sodium Pool
Xiaoxue Huang, Shuisheng He (Univ of Sheffield)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2850-2863
Experimental and Numerical Investigation for Geometrical Effect on the Flow Characteristics for Plate-Throttle Entry Tube of Fast Reactor Fuel Assembly
Haiqi Qin, Daogang Lu, Cong Wang, Dawen Zhong, Yu Wang, Siyu Lyu (NCEPU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2864-2877
Design of a Direct Reactor Auxiliary Cooling System (DRACS) Considering Tritium Management for Advanced High-Temperature Reactor (AHTR)
Sheng Zhang, Hsun-Chia Lin, Keyong Cheng, Xiaodong Sun (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2878-2891
Advancing Radiative Heat Transfer Modeling in High-Temperature Liquid-Salts
C. Coyle, E. Baglietto, C. Forsberg (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2892-2904
Assessment on the Practicality of Off-the-Shelf Valves for Use in Molten Salt
T. K. Howard, David Holcomb, Kevin Robb (ORNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2905-2917
Assessment of Severe Accident Management by Multiple Mitigation Actions Using Monte Carlo Sampling
Wonjn Choi, Nam Kyung Kim, Joongoo Jeon, Sung Joong Kim (Hanyang Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2918-2929
Effect of Water Radiolysis on the Heat Pipe Under Gamma Ray Irradiation for Fukushima Daiichi Decommissioning Use
Yao Zhang, Takayuki Saimu, Shunichi Suzuki, Koji Okamoto (Univ of Tokyo)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2930-2942
PMSYS: Plant Management System as a Part of Swiss Simulation Platform
K. Nikitin, I. Clifford, H. Ferroukhi (PSI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2943-2954
Risk-Informed Safety Analysis for Accident Tolerant Fuels
C. Parisi, Z. Ma, D. Mandelli, N. Anderson, H. Zhang (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2955-2968
Transient Analysis of a Detailed Thermal-Hydraulic Model of a VVER-1000 Core with the System Code ATHLET
Y. Périn, R. Henry, K. Velkov (GRS), S. P. Nikonov (Mephy)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2969-2979
CATHARE 3D Modeling Capability of a Small-Scale Pool Test Rig Experiments
A. Bousbia Salah (Bel V), J. Martin (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2980-2991
Investigation of Drag and Virtual Mass Coefficients for Rising Ellipsoidal Bubbles
Alexander Dueñas, Isaiah Wieland, Wade Marcum, Qiao Wu (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 2992-3004
Methodology for Experimental Identification of Mixing Characteristics in the Primary System of PWR
D.-J. Euh (KAERI/Univ of Science and Technol), K. H. Kim, W. M. Park, H. S. Choi,Y. J. Youn (KAERI)S. S. Lee, S. K. Lim, H. D. Lee (Korea Hydro & Nuclear Power Co.), T. S. Kwon (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3005-3013
Assessment, Implementation, Validation, and Verification of Interfacial Closures in Multiphase Flows for the CFD Codes FLUENT and CFX
Gustavo Montoya, Jay Sanyal (ANSYS, Inc.), Markus Braun (ANSYS Germany GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3014-3029
The Evaluation of AP1000® Plant Cold Leg Thermal Stratification During PRHR HX Natural Circulation Test
Hong Xu, Natalie M. Rodgers Richard F. Wright, John W. Boufford, (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3030-3041
Validation of Condensation Models for Hydrogen Distribution Evaluation Using CFD
Noriaki Hamada, Masataka Hidaka (Hitachi, Ltd.), Tadashi Fujii, Takeshi Yamada (Hitachi-GE, Ltd)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3042-3053
Development of a Systematic Approach for Quantification of Thermal-Hydraulic Code Model Input Uncertainty
Jean Baccou (IRSN), Jinzhao Zhang (Tractebel Engineering S.A.), Philippe Fillion, 27645Guillaume Damblin (CEA), Alessandro Petruzzi (NINE), Rafael Mendizábal (CSN), Francese Reventos (UPC),Tomasz Skorek (GRS), Mathieu Couplet, Bertrand Looss (EdF R&D), Deong-Yeon Oh (KINS), Takeshi Takeda (Nuclear Regulation Authority), Nils Sandberg (OECD NEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3054-3067
Nuscale Safety Analysis Code and Design Validation Test Program
Matt Kizerian, Bradyn Wuth, Cristhian Galvez Velit, Maggie Wang, Robert Houser (NuScale Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3068-3077
Departure from Nucleate Boiling (DNB) Simulations Base on an Interface Tracking Method
Y. Sato, B. Niceno (PSI), B. L. Smith (Goldsmith Transactions), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3078-3091
MultiPhysics for Nuclear Energy Applications Using a Cohesive Computational Framework
R. Martineau, D. Andrs, R. Carlsen, D. Gaston, J. Hansel, F. Kong, A. Lindsay, C. Permann, A. Slaughter (INL), E. Merzari, Rui Hu (ANL), A. Novak, R. Slaybaugh (Univ of California, Berkeley), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3092-3106
Status and Challenges of SCWR Thermal Hydraulics Research in China
Xiaojing Liu (Shanghai Jiao Tong Univ), Xu Cheng (KIT), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3107-3125
Severe Accident Phenomena: A Comparison Between NuScale, Other Advanced LWRs, and Existing LWRs
Scott J. Weber, Etienne M. Mullin (NuScale Power, LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3126-3139
Nucleate Boiling Simulation Using Interface Tracking Method
Mengnan Li, Igor Bolotnov (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3140-3153
CFD Prediction of Ultra-High Critical Heat Flux for Subcooled Water Flow Boiling in a Vertical Tube
Kai Wang, Nejdet Erkan, Koji Okamoto (Univ of Tokyo)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3154-3167
Numerical Study on the Dynamics of Bubble in Divergence of Venturi Tube
Yuchen Song, Junlian Yin, Dezhong Wang, Kangbei Cai (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3168-3181
Improving the Understanding of Subgrid-Scale Deposition for Implementation in M-CFD Applications
G. Agostinelli, E. Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3182-3194
A CFD Study on the Hydrodynmics for Tandem Plate Configurations Under Turbulent Flow
Wade Marcum, Jonathan Gjemso (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3195-3205
CFD Analysis of the Fluid Flow, Heat Transfer and Cladding Oxidation in a PWR Fuel Bundle
Dong-Yuan Sheng (Westinghouse Electric Sweden AB/KTH), Marcus Seidl (PreussenElektra GmbH), Zhouqi Du (Technical Univ Munich)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3206-3218
Framatome’s Unified Single-Phase CFD Methodology for Fuel Design and Analysis
A.Hatman, S. Lydzinski, L. Charlot, G. Bache (Framatome), B. Farges (Framatome SAS), J. Dumond, M. Rehm, K. Vogel (Framatome GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3219-3232
Thermal Analysis for eVinciTM Micro Reactor
Hong Xu, Jurie J. Van Wyk, Richard F. Wright (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3233-3242
Numerical Simulation of Penetration Flow into T-Junction Branch Lines
Y. Utanohara, K. Miyoshi, M. Kamaya (Inst of Nuclear Safety System, Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3243-3256
Statistical Emulator Models for Scalar Mixing in Reactor Safety Analysis
A. Gairola (Kansas State Univ), W. Guo, B. Niceno (PSI), H. Bindra (Kansas State Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3257-3269
Universal Digital Nuclear Reactor System (UNDREAS)
Chirayu Batra, Vladimir Kriventsev (IAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3270-3279
Numerical Investigation of the Transient Flow with Alternating Diagonal Flow Direction in Wall Bounded Inline Tube Bundles
Weikai Gao, Xiaowei Li, Xinxin Wu (Tsinghua Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3280-3291
Transient Local Thermal Hydraulics Data for Two-Phase Flow Instability in Natural Circulation
Taiyang Zhang, Zhiee Jhia Ooi, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3292-3301
Natural Circulation of Sodium, Lead, LBE, Helium and Molten Salt Cartridge Closed Loops
S. A. Balderrama Prieto (OSU), P. Sabharwall (INL), M. Farmer (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3302-3314
Propagation of Stratified Density Fronts in the HiRJet Facility
Daniel Nunez, Victor Petrov, Annalisa Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3315-3328
Development of a Polyhedral Staggered Mesh Scheme Application to Subchannel and CFD SFR Thermal Hydraulics
Antoine Gerschenfeld, Yannick Gorsse, Gauthier Fauchet (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3329-3342
Visualization of Flow Inside Reactor Vessel Using 1/5-Down Scaled Model of Prototype Gen-IV Sodium Cooled Fast Reactor
Woo Shik Kim, Yong Seok Choi, Dong-Jin Euh (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3343-3354
Study on Multi-Dimensional Core Cooling Behavior of Sodium Cooled Fast Reactors Under DRACS Operating Condition
T. Ezure, T.Onojima, M. Tanaka, J. Kobayashi, A. Kurihara (JAEA), Y. Kameyama (NDD Cooporation)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3355-3363
Experimental Study on Heat Dissipation of Spent Fuel Assembly of Sodium Fast Reactor During Defueling
Zenghui Wu, Jinbiao Xiong, Xiang Chen (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3364-3377
Heat Transfer Deterioration and Enhancement in the Thermal Entry Length of Laminar Supercritical Water Channel Flow
R. Barney (LLNL/Univ of California, Berkeley), R. Nourgaliev (LLNL), J. P. Delplanque (Univ of California, Davis), R. McCallen (LLNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3378-3390
The Preliminary Safety Analysis of a s-CO2 Brayton Cycle Cooled Reactor System
Chuntian Gao, Pan Wu, Jianqiang Shan (Xi’an Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3391-3401
A Study in the Effect of External Vertical Acceleration on the Uniformly Heated Channel with Supercritical Water
Jin-Der Lee, Shao-Wen Chen (Natl Tsing Hua Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3402-3415
PIV Refinement Using Optical Flow for High Resolution Flow Measurement: Development and Preliminary Validations
Jee Hyun Seong (MIT), Min Seop Song, Eung Soo Kim (Seoul Natl Univ), Daniel Nunez, Annalisa Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3416-3429
Accelerating Infrared Boiling Heat Transfer Studies with Online Machine Learning Capabilities
M. Ravichandran, M. Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3430-3442
Experimental Investigation of Bubble Nucleation, Growth and Departure Using Synchronized IR Thermometry, Two-Color LIF and PIV
Gustavo M. Aguiar (MIT), Victor Volgaropoulos, Omar K. Matar, Christos N. Markides (Imperial College London), Matteo Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3443-3450
Scaling Analysis on the Coolability of Fuel Rods and Debris Beds with Seawater
Zayed Ahmed, Hitesh Bindra, Steven Eckels (Kansas State Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3451-3463
How Much Was Hydrogen Gas Burned in the 1F3 Explosion
Wison Luangdilok (Fauske & Associates, LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3464-3472
Void Fraction Distribution in a Header-Feeder Test Facility Under a Simulated Loss-of-Coolant Accident
Étienne M. Lessard, Jun Yang (CNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3473-3486
An Analytical Model of Plume/Droplet Interactions for the Assessment of Spent-Fuel-Pool Spray Cooling Effectiveness
J. Martin (IRSN), N. Tsukamoto (NSA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3487-3500
Experimental and Numerical Research on Melting Behavior Mechanism of Fuel Rod Using MPS-CV Method
Wenxi Tian, Yonglin Li, Tangtao Feng, Ronghua Chen, Suizheng Qiu, G. H. Su (Xi’an Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3501-3511
Experimental Investigation of Debris Bed Relocation Behavior by Bottom Gas-Injection
Chunming Teng, Bin Zhang, Jianqiang Shan (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3512-3529
Numerical and Experimental Investigation of the Water Flow Through PWR Spacer Grids at the Brazilian Nuclear Technology Development Center
H. F. P. Castro (UFMG), G. A. M. Vidal, T. A. S. Vieira, V. V. A. Silva, D. A. M.Campolina, G. P. Barros (CDTN), M. A. F. Veloso (UFMG), A. A. dos Santos (CDTN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3530-3541
Validation of Risk-Informed Safety Margin Characterization for Flooding of Nuclear Power Plants
M. André, P. Bardet (George Washington Univ), R. Sampath, N. Montanari (Centroid Lab), L. Lin (NCSU), S. Prescott, E. Ryan (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3542-3553
High-Resolution High-Speed Void Fraction Measurements in Helical Tubes Using X-Ray Radiography
David Breitenmoser (Univ of Michigan/ETHZ), Annalisa Manera (Univ of Michigan), Horst Prasser (ETHZ), Victor Petrov (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3554-3567
CFD Validation of Buoyancy Driven Jet Spreading, Mixing and Wall Interaction
Graham Macpherson (Frazer-Nash Consultancy), Ryan Tunstall (Rolls-Royce)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3568-3581
Uncertainty Quantification and Reduction for Multiphase-CFD Solvers: A Data-Driven Bayesian Approach Supported by High-Resolution Local Measurements
Yang Liu, Xiaodong Sun (Univ of Michigan), Yang Liu (Virginia Tech), Nam Dinh (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3582-3597
Verification and Validation of COMSOL for Heat Transfer in Thin Rectangular Channels Using NACA Test Results
T. K. Howard, P. Jain, E. Popov (ORNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3598-3611
Modeling Gamma and Neutron Heating to a Liquid Hydrogen Tank for Nuclear Thermal Propulsion with RELAP5-3D
R. P. Martin (BWX Technol), J. A. Caffrey, M. G. Houts (NASA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3612-3623
Evaluation of a Desuperheating Spray Chamber for a Scaled Nuclear Thermal Propulsion Rocket Exhaust Capture System Test
R. P. Martin, J. L. Gustafson (BWXT), D. J. Coote (NASA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3624-3636
Numerical Investigations on the Turbulent Prandtl Number Models for Internal Forced Convection to Low-Pr Helium-Xenon Mixtures
Biao Zhou, Jun Sun, Yuliang Sun, Yu Ji (Tsinghua Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3637-3648
Progress Toward Simulating Departure from Nucleate Boiling (DNB) at High Pressure Applications with Selected Wall Boiling Closures
Seung Jun Kim, Mario R. Naranjo, Russell C. Johns (LANL), Emilio Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3649-3662
Exploring Two-Phase Flow Regime Transition Mechanisms Using High Resolution Virtual Experiments
Matthew D. Zimmer, Igor A. Bolotnov (NCSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3663-3676
Simulations of Particle Transport Inside Bubbles Using Coupled Interface and Lagrangian Tracking Approaches
Min Zhu (Nanjing Univ of Science and Technology), A. Dehbi Y. Sato, B. Niceno (PSI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3677-3688
Numerical Simulation Investigation on Two-Phase Flow Instabilities in Two-Parallel-Channel
Jianping Long (Xi’an Jiaotong Univ), Baowen Yang (Xi’an Jiaotong Univ/Delta Energy Group), Sipeng Wang (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3689-3704
Application of the COBRAG Subchannel Code to Fuel Design
S. Oh, B. Hizoum, K. Kang, D. Miranda, J. Andersen, S. Bowman (GE Hitachi Nuclear Energy)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3705-3718
Transient Subchannel Analysis of BWR Fuel Thermal Hydraulic Performance
B. Hizoum, D. Miranda, K. Kang, S. Oh, J. Andersen, S. Bowman (GE Hitachi Nuclear Energy)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3719-3731
Experimental Thermal-Hydraulic Study of a Steam-Droplets Flow Inside a Vertical Pipe?Application to LOCA in PWR Reactor
J. D. Peña Carrillo, A. V. S. Oliveira, T. Glantz (IRSN), M. Gradeck, Al. Labergue, (Univ of Lorraine)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3732-3740
Hybrid Nodal Integral -Finite Element Method (NI-FEM) for 2D, Time-Dependent Burgers’ Equation in Arbitrary Geometries
Sundar Namala, Rizwan-Uddin (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3741-3755
Application of Computational Fluid Dynamics (CFD) Codes For Nuclear Power Plant Design
M. Krause (IAEA), B. Smith (Goldsmith Transactions), T. Hoehne (HZDR), W. K. In (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3756-3769
Density Wave Instability Verification of CFD Two-Fluid Model
S. L. Sharma, M. A. Lopez de Bertodano (Purdue Univ), J. R. Buchanan (NNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3770-3778
Remaining Issues in System Thermal Hydraulics How the Fonesys and CONUSAF Networks Can Help Find Solutions?
D. Bestion (Consultant), F. d’Auria (Univ di PISA), Y. Hassan (Texas A&M), N. Aksan (Scientific Consultant), M. Lanfredini (Univ di PISA), K. D. Kim (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3779-3791
A New Approach of Studying Transient Critical Heat Flux Using Computational Fluid Dynamics
T. Chen, Wade Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3792-3805
A New Hypothesis of Transient Boiling Based on the CFD Simulation and Past Experimental Studies
T. Chen, W. Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3806-3819
SPH Simulation on Single Bubble Behavior in Linear Shear Flow
Yelyn Ahn, Young Beom Jo, So Hyun Park, Jin Woo Kim, Eung Soo Kim (Seoul Natl Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3820-3832
Improved Design of Spent Fuel Dry Storage Using Phase Change Heat Transfer of Hybrid Control Rod-Heat Pipe
Kyung Mo Kim, In Cheol Bang (UNIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3833-3843
Experimental Investigation on Atmospheric, Passive Spent Fuel Pool Cooling by Two-Phase Closed Thermosyphons
Claudia Grass, Rudi Kulenovic, Jöerg Starflinger (Univ of Stuttgart)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3844-3855
Buoyancy-Driven Transformations in a Thermal Striping Flow Field
S. Lomperski, A. Obabko E. Merzari, (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3856-3864
Thermal Hydraulic Design of an In-Pile Experimental Loop for Fast Test Reactor Conditions
Anton Higgins, Dan LaBrier, Wade Marcum,Ben Lilley, Todd Palmer (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3865-3878
Computational Fluid Dynamics Assessment of Proposed Axial Reflector Designs for the Versatile Test Reactor Using Nek5000
D. R. Shaver, H. Yuan, F. Heidet (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3879-3892
Integrated Simulation Capabilities for Thermal Hydraulic Analysis of Test Vehicles in the Versatile Test Reactor
A. J. Brunett, T. Q. Hua, G. Hu, R. Hu, T. H. Fanning, G. Zhang (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3893-3907
Transient Analysis of an FHR Coupled to a Helium Brayton Power Cycle
Guolei Zhang (Harbin Eng Univ), Minghui Chen, Xiaodong Sun (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3908-3921
Molten Salt Coolant Modeling In TRACE
Glenn Roth, Jay Spore (Information Systems Laboratories)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3922-3930
CFD Simulation of Xenon Removal by Helium Bubble Sparging in Molten Salt
Jiaqi Chen, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3931-3944
Flow Rates in a Natural Circulation FLiBe Loop
Karl Britsch, Mark Anderson, Kumar Sridharan (Univ of Wisconsin, Madison)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3945-3954
Uncertainty Analysis of PIV Measurements for Liquid Velocity in Two-Phase Bubbly Flows
Yang Liu, Yalan Qian, Chengqi Wang, Xiaodong Sun (Univ of Michigan), Yang Liu (Virginia Tech)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3955-3967
Characterization of Liquid Jet Breakup for the Simulation of Accidental Sodium Leakage Scenarios in Sodium-Cooled Fast Reactors
Mira Sadek, Thierry Gilardi (CEA), Rudy Bazile (IMFT), Stéphane Mimouni, Lynda Porcheron (EdF R&D)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3968-3977
Important Issues in Validation of Computational Fluid Dynamics Codes Against CFD Grade Experimental Results
C. W. Hollingshead, A. Rashkovan (NRCN), A. Maunsell, M. Hodgins, D. R. Novog (McMaster Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3978-3988
Preliminary Results on the Development of a Fast-Neutron Tomography System for Void Fraction Distribution Measurements
G. G. Patterson, D. R. Novog (McMaster Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 3989-4003
Ex-Vessel Fuel Coolant Interaction Experiment with the Geometry of an AP1000 Reactor
Giancarlo Albrecht, Leonhard Meyer (KIT), Rongjin Zhang (SPICRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4004-4017
Premixed Layer Formation Modelling in Stratified Melt-Coolant Geometry
Janez Kokalj, (Jozef Stefan Inst/Univerza v Ljubljani), Matjaž Leskovar, Mitja Urši? (Jozef Stefan Inst)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4018-4031
Risk of Containment Failure Due to Ex-Vessel Steam Explosion for Nordic BWRs
Dmitry Grishchenko, Sergey Galushin, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4032-4038
Melt Droplet Fragmentation Behavior During Fuel-Coolant Interaction
Gen Li, Haobo Feng, Panpan Wen, Jun Zhang, Jinshi Wang, Junjie Yan (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4039-4049
Dispersion of Surrogate LWR Fuel Experiments Under LOCA Conditions
G. D. Latimer, W. R. Marcum (OSU), W. F. Jones (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4050-4062
A Summary of Fission-Product Transport Phenomena During SGTR Severe Accidents
T. Lind (PSI), S. Campbell (NRC), L. E. Herranz (CIEMAT), M. Kissane (OECD/NEA), JinHo Song (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4063-4075
Simulation of In-Vessel Retention Scenarios in PWR with ATHLET-CD
P. Pandazis, S. Weber (GRS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4076-4086
Managing a Station Blackout (SBO) at the INKA Test Facility with Nothing but Passive Technology
Thomas Wagner, Thomas Mull (Framatome GmbH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4087-4097
Digitilization and Management of Thermal Hydraulic Legacy Data Using FPoliDON Platform
Cesare Frepoli (FPoliSolutions LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4098-4108
Revisiting the PIRT and Scaling Analysis Within the Frame of 3D System Code Modelling
D. Bestion (Consultant), P. Fillion (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4109-4122
Application of Adjoint Based Node Optimization Method to Nuclear Thermal-Hydraulic System Analysis Code
Jae Jun Lee, Seongmin Son, Min-Gil Kim, Jeong Ik Lee (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4123-4136
Preliminary Tasks to Integrate CATHARE_2 3D Reactor Vessel Module in Real-Time Simulators at EDF/DT
David Pialla, Marc Ludmann, Karine Vareille (EdF)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4137-4149
A Rotodynamic Pump Seizure Transient Simulated Using the CATHARE-3 One-Dimensional Pump Model
L. Matteo, G. Mauger (CEA), P. Gyomlai (Framatome), A. Dazin (LMFL), N. Tauveron (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4150-4163
Multiscale and Multiphysics Simulation of Sodium Fast Reactors: From Model Development to Safety Demonstration
Antoine Gerschenfeld (CEA), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4164-4177
Molecular Tagging Velocimetry: Pushing the Limits of Velocimetry
P. M. Bardet, C. Fort, M. A. Andre (George Washington Univ), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4178-4183
Overview of Thermal-Hydraulic Validation Tests with SMART-ITL to Support SMART Pre-Project Engineering
Hyun-Sik Park, Hwang Bae, Sung-Uk Ryu, Jin-Hwa Yang, Byong-Guk Jeon, Yoon-Gon Bang, Sung-Jae Yi (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4184-4196
Comparison of Two Different Sized Small Break LOCAs on the Passive Safety Injection Line with SMART-ITL
Jin Hwa Yang, Hwang Bae, Sung-Uk Ryu, Byong Guk Jeon, Sung-Jae Yi, Hyun-Sik Park (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4197-4210
Hot Spot Temperature Prediction for a Micro Modular High Temperature Gas-Cooled Reactor
Sung Nam Lee, Nam-il Tak, Chang Keun Jo (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4211-4218
Development of a SCDAP/RELAP5 Model for the Simulation of the Helical-Coiled Once-Through Steam Generators
Ziyi Xu, Maolong Liu, Yao Xiao, Hanyang Gu (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4219-4232
Flow Dynamic Behavior in Rod Bundles: An Experimental Assessment
O. C. A. Nalin, P. Lazo (CNEA), C. P. Marcel (CONICET), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4233-4245
Effect of Part-Length Rods and Transient Flow for Different BWR Subchannel Geometries
Lukas Robers, Horst-Michael Prasser (ETH Zürich)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4246-4259
Unsteady Pressure and Velocity Measurements in 5x5 Rods Bundle Using Grids with and Without Mixing Vanes
N.Turankok, F. Bazin, V. Biscay, T. Lohez, F. Moreno, S. Testanière, Lionel Rossi (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4260-4272
Experimental Investigation of Power Transient Critical Heat Flux for Downward Flow in Narrow Rectangular Channel Used in Research Reactor
Hui Yung Kim, Jae Jun Jeong, Byong Jo Yun (Pusan National Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4273-4286
A Three-Dimensional PWR LBLOCA Simulation Using the CUPID Code
Ik Kyu Park, Han Young Yoon, Seung Jun Lee, Yun Je Cho, Jae Ryong Lee (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4287-4298
Advanced Modelling Capabilities for Pin-Level Subchannel Analysis of PWR and VVER Reactors
Manuel Garcia, Uwe Imke, Diego Ferraro, Victor Sanchez-Espinoza, Luigi Mercatali (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4299-4309
Chimney and Diverging Effects in Core PWR: Analysis and Experimental Characterization for Predictive Behaviour During Loss of Coolant Accident
Christophe Rabe, Raphaël Préa (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4310-4323
CFD Analysis of Hydrogen Flame Acceleration with Burning Velocity Models
K. Motegi, N. Trianti, T. Matsumoto, T. Sugiyama, Y. Maruyama (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4324-4335
Numerical Investigation of the Effect of Buoyancy Forces on the Deflagration of Hydrogen in the THAI Facility
A. Attavino, L. Koloszar, P. Planquart (Von Karman Inst), M. Adorni (BelV), A. Parente (Université libre de Bruxelles)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4336-4347
Development of a Radionuclide Release Module for an Integrated Source Term Analysis Tool for Liquid Metal Cooled Fast Reactors
T. Q. Hua (ANL), S. J. Lee (Fauske & Associates, LLC), J. Liao (Westinghouse), A. Moisseytsev (ANL), P. Ferroni (Westinghouse), A. Karahan (ANL), C. Y. Paik (Fauske & Associates, LLC), A. M. Tentner, T. Sofu (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4348-4361
Numerical Study of Lean Limit Hydrogen Flames Propagating Upward to Validate a Flammability Limit Model
Joongoo Jeon, Hoichul Jung, Yeon Soo Kim, Sung Joong Kim (Hanyang Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4362-4371
Preliminary RELAP5 System Analysis of the Water-Based NSTF?Part 1: Model Development
Q. Lv, A. Kraus, R.Hu, M. Bucknor, D. Lisowski (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4372-4387
Preliminary RELAP5 System Analysis of the Water-Based NSTF?Part 2: Parametric Study
Q. Lv, A. Kraus, R.Hu, M. Bucknor, D. Lisowski (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4388-4405
Turbulent Natural Convective Condensation on the Underside of Inclined Surfaces for the AP1000® Plant Containment
Matthew M. Swartz, John Lojek, Richard F. Wright, Ryan T. Vanston (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4406-4417
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
Simon Li, Antoine Gerschendfeld (CEA), Olivier Bernard, Thomas Sageaux (Framatome)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4418-4429
Modelling of the DIADEMO Experiment with the CATHARE Code for ASTRID Gas Power Conversion System Studies
G. Mauger, M. Hochart, B. Grosjean, P. Taraud, B. Morassano (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4430-4442
Oscillation Phenomenon Study for the Anti-Siphon Equipment in CFR600 Design
Yan Peng (China Inst of Atomic Energy)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4443-4456
Validating System Analysis Module (SAM) Models Using Natural Circulation Experimental Data
Hsun-Chia Lin (Univ of Michigan), Rui Hu (ANL), Xiaodong Sun (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4457-4469
Modelling the Draining of a Molten Chloride Salt Reactor
Emily Lewis, Gregory Cartland-Glover, Stefano Rolfo, Charles Moulinec, David R. Emerson (STFC), Bruno Merk (Univ of Liverpool)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4470-4483
Progess in the Thermal Hydraulic Modeling of the Molten Salt Fast Reactor
M. Tano, P. Rubiolo (Univ of Grenoble-Alpes), J. Ragusa (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4484-4497
Measurements of Boiling Heat Transfer, Time-Averaged Void Fraction Distributions Using Neutron Radiography
Abir Muhammad. Boris Khaykovich, Jan Petrik, Artyom Kossolapov, Bren Phillips, Matteo Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4498-4504
Automatic Detection of Bubble Footprints and Dry Spots in Infrared Boiling Heat Transfer Investigations Using Deep Convolution Neural Networks
Muhammad Abir (MIT), Shaikat M. Galib (Missouri Univ Sci Technol), Jee Hyun Seong, Matteo Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4505-4517
Ultrasound Measurement of Upward Liquid Film Flow in Vertical Pipe
Yuki Wada, Akira Satou, Yasuteru Sibamoto, Taisuke Yonomoto (JAEA), Jun Sagawa (Mito Electronic Solution)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4518-4531
High-Fidelity Velocity Measurements in a Totally Blocked Subchannel of a Wire-Wrapped 61-PIN Hexagonal Fuel Bundle
L. A. Lance, Nolan Goth White, Jake Pettyjohn, D. T. Nguyen, R. Vaghetto, Y. A. Fuel Coolant Interaction, Modeling and Experiments?IIHassan (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4532-4541
New Film Boiling Correlations for Drops and Fragments in Fuel Coolant Interaction Codes
E. De Malmazet (EdF)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4542-4555
Effects of Salinity in Coolant on Steam Explosion
Qiang Guo, Louis Manickam, Weimin Ma, Sevostian Bechta (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4556-4567
Validation of a Full Model for the Analysis of Ex-Vessel Steam Explosion in LWRs
Dmitry Grishchenko, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4568-4574
Predictability of System Codes for Void Fraction in Bundle
Yunseok Lee, Yeongjae Lee, Taewan Kim (Incheon National Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4575-4586
Benchmark Simulation of the Natural Convection Shutdown Heat Removal Test Facility Using SAM
B. Hollrah, R. Hu, M. Bucknor. D. Lisowski (ANL), Y. Hassan, R. Vaghetto (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4587-4600
Validation of S3K Against the Olkiluoto 2 Pump Trip Event May 8th 2018
Christian Jönsson, Gerardo Grandi (Studsvik Scandpower), Aarno Isotalo, Ville Hynönen (Teollisuuden Voima Oyj)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4601-4614
Validation and Uncertainty Quantification for Two-Phase Natural Circulation Flows Using TRACE Code
K. Borowiec, T. Kozlowski, C. S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4615-4623
First Assessments of the Dynamic Gap Conductance Model in TRACE
I. Clifford, C. Cozzo, H. Ferroukhi (PSI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4624-4636
The New Critical Discharge Model for ATHLET
T. Skorek (GRS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4637-4649
An Enhanced Property File for RELAP5-3D
J. Luitjens, K. Schmidt, B. Wolf (NuScale Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4650-4664
Development of a Thermal-Hydraulic Analysis Code for Helically Coiled Once Through Steam Generator
Jun Huang, Junli Gou, Jianqiang Shan (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4665-4680
A Three-Dimensional Multi-Physics Analysis of the Steam Line Break Accident of a PWR Using CUPID-RV/MASTER
Jae Ryong Lee, Ik Kyu Park, Seung Jun Lee, Yun Je Cho, Yong Hee Choi, Han Young Yoon (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4681-4689
Applicability of Gothic 8.3(QA) for Non-LWR Simulation, Aerosol Modeling and Hydrogen Management
J. W. Lane, T. L. George, S. W. Claybrook, J. A. Zankowski (Zachry Nuclear Eng, Inc.), T. Kindred (EPRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4690-4703
Critical Heat Flux Model for Vertical Annular Mist Flow Conditions in a Rod Bundle
José N. Reyes, Jr. (NuScale Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4704-4719
A Criterion to Classify Void Fraction Profiles in Adiabatic Bubbly Flows Based on Averaged Flow Quantities for Use in Subchannel Codes
Ravikishore Kommajosyula (MIT), Guillaume Bois, Alan Burlot, Maria Giovanna Rodio, Benjamin Cariteau (CEA), Emilio Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4720-4731
Mapping Coherent Thermal Structures in a Rod Bundle
S. Lomperski, J. Licht (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4732-4740
Investigations of Neutron Noise Induced by Transient Cross Flow in a PWR Reactor Core
Zhuoqi Du (Technical Univ Munich), Dong-Yuan Sheng (Westinghouse Electric Sweden AB), Marcus Seidl (PreussenElektra GmbH), Rafael Macián-Juan (Technical Univ Munich)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4741-4754
On the Use of Small-Scale LES for Full-Length Heated Fuel Rod Simulations
Javier Martinez, Elia Merzari (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4755-4768
Subchannel Analysis of Mixed Convection in a Rod Bundle
Ting Wu, Baowen Yang (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4769-4779
Addressing the Usage of CFD Within the CSAU Framework for Nuclear Reactor Safety Analysis Simulations
Michael Acton, Emilio Baglietto (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4780-4794
Inverse Uncertainty Quantification by Hierarchical Bayesian Inference for TRACE Physical Model Parameters Based on BFBT Benchmark
Chen Wang (Univ of Illinois), Xu Wu (MIT), Tomasz Kozlowski (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4795-4807
A Study on Coupling Calculation Convergence Criterion Based on Uncertainty Analysis
Xiaolie Wang, Jianjun Wang, Zhiqiang Zhu (Harbin Eng Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4808-4816
About Phenomena Identification in a PIRT
D. Bestion (Consultant)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4817-4830
Analytical Solution to a One-Dimentional Two-Region Heat Conduction Problem with Time Dependent Heat Input
Yikuan Yan, Emory Brown, Wade Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4831-4840
Transient Analyses of the Versatile Test Reactor Using RELAP5-3D
C. Parisi, C. Davis, G. Youinou (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4841-4853
Modelling Thermal Stratification in Upper Plenum of Sodium Fast Reactor Using Systems Code SAS4A/SASSYS-1 and Using CFD
Sundar Namala, Rizwan-Uddin (Univ of Illinois), Tyler Sumner (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4854-4863
Validation of the MATHYS Tool for the Design of Sodium-Cooled Fast Reactors Using PHENIX End-of-Life Test Data
Clotaire Geffray, Antoine Gerschenfeld, Yannick Gorsse (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4864-4875
Molten Salt to Supercritical CO2 Diffusion-Bonded Heat Exchanger Testing to Support Component Certification for Advanced Nuclear Power Systems
Shaun R. Aakre, Mark H. Anderson (Univ of Wisconsin, Madison)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4876-4887
Triple Flow Heat Exchanger with Intermediate Oval Twisted Tube for FHRs
Amir Ali, Bryan Wallace, Edward D. Blandford (Univ of New Mexico)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4888-4898
3D Coupled Transient Simulation of a Fast Liquid Fuel Molten Salt Reactor Primary Loop Using GeN-Foam
Muhammad Altahhan, Sandesh Bhaskar, Paolo Balestra, Jason Hou, Maria Avramova (NCSU), Nicholas Smith (Southern Co.), Carlo Fiorina (EPFL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4899-4911
Application of Strain Gages in a Highly Advective Environment for Measurement of Fluid-Structure Interactions
A. W. Weiss, W. R. Marcum (OSU), W. F. Jones, A. M. Phillips, T. V. Holschuh (INL), T. K. Howard (ORNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4912-4925
An Approach to Instrumenting a Full-Scale 61-Pin Hexagonal Fuel Bundle for Flow-Induced Vibration Testing
C. A. Nixon, W. R. Marcum, A. W. Weiss (OSU), K. M. Steer, R. B. Jackson, M. G. Martin, C. Yeager (TerraPower)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4926-4933
Investigation on the Characteristics of Melt Jet Breakup in Water with Both Experiment and LBM Methods
Hui Cheng, Jiyun Zhao (City Univ of Hong Kong)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4934-4947
Fuel-Coolant Interaction Modeling Supporting TREAT Experimental Analysis
R. Armstrong (Univ of Wisconsin/INL), H. Jo, M. L. Corradini (Univ of Wisconsin, Madison)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4948-4960
Experimental Study on the Molten Materials Effect in Fuel-Coolant Interaction
Pengfei Liu, Longkun He, Bo Kuang (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4961-4970
Parametic Studies on CHF Trends for a Downward Facing Curved Geometry Under a Flow Condition
Jun Yeong Jung, Dong Hoom Kam, Yong Hoon Jeong (KAIST), Hae Min Park (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4971-4982
Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop
Daniel P. LaBrier, Yikuan Yan, Emory Brown, Wade R. Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4983-4993
Study on Fuel Damage Progression and Porosity in the SFD 1-4 Test
K. Nishida, N. Sano, T. Torige, T. Kusunoki, M. Murase (Inst of Nuclear Safety System, Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 4994-5005
Heat Transfer Model at Interface Between Molten Core and Concrete for Anisotropic Ablation
Kyoung M. Kang (Univ of Wisconsin, Madison/GE Hitachi Nuclear), Michael L. Corradini (Univ of Wisconsin, Madison), Mitchell T. Farmer (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5006-5019
Inter-System Loss of Coolant Accident (ISLOCA) of APR1400 with Severe Accident Condition
Byeonghee Lee, Kwang Soon Ha (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5020-5028
H2020 MYRTE Circe-Hero Experimental Campaign: Post-Test Activity and Code Validation
D. Castelliti, T. Hamidouche (SCK-CEN), P. Lorusso (Univ of Roma), M.Tarantino (ENEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5029-5042
MARS-KS Code Assessment on LOCA Test in Pressurized Water Loop Facility of PHWR
S. O. Yu, M. K. Cho, S. C. Song, K. L. Baek (KINS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5043-5051
Data Assimilation with Subchannel Analysis Code CTF on NUPEC BWR BFBT Test Matrix
Atsushi Ui, Yoshiro Kudo, Masahiro Furuya (CRIEPI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5052-5063
Horizontal Stratification and Its Application to PWR LOCA Analysis
Jun Liao (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5064-5077
Numerical Study of Flow-Induced Vibration of Nuclear Fuel Rods
D. De Santis, A. Shams (NRG)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5078-5091
Numerical Simulations of the Turbulence-Induced Vibrations of a Wire-Wrapped Hexagonal Fuel Assembly
H. Dolfen, J. De Ridder (Ghent Univ), L. Brockmeyer, E. Merzari (ANL), G. Kennedy, K. Van Tichelen (Belgian Nuclear Research Centre), J. Degroote (Ghent Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5092-5102
Elastic Vibration Characteristics of Strips in Turbulent Water Flow
Botao Zhang, Yechen Zhu, Shengjie Gong, Hanyang Gu, Zhenqin Xiong (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5103-5115
Smaller and Safer: How Micro-Reactors Can Redefine Nuclear
Ken Canavan, Yasir Arafat, Ryan Blinn (Westinghouse), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5116-5125
Challenges in Containment Thermal Hydraulics
E. Studer, D. Abdo, S. Benteboula, G. Bernard-Michel, B. Cariteau, N. Coulon, F. Dabbene, Ph. Debese, S. Koudriakov, C. Ledier, J.-P. Magnaud, O. Norvez, J.-L. Widloecher, A. Beccantini, S. Gounand, J. Brinster (CEA), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5126-5140
Fuel Assembly Bow Evaluations with Computed Hydraulic Forces
Robert A. Brewster, Yuriy Aleshin (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5141-5150
Development, Verification and Validation of the Multi-Scale CATHARE?NEPTUNE_CFD Coupling
Clotaire Geffray (CEA), Chaï Koren (EdF R&D)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5151-5164
Multi-Scale Coupling of TRACE and TrioCFD Based on ICoCo
K. L. Zhang (KIT), X. L. Zhang (KIT/USTC), V. H. Sanchez Espinoza, R. Stieglitz (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5165-5178
Analyses of the Flow Mixing Phenomena in a Pressurized Water Reactor by 1d- and Coupled 1d-3d Simulations
H. V. Hristov, J. Herb, A. Papukchiev (GRS)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5179-5192
Film Thickness and Disturbance Wave Structure of Upward Annular Flow
Guanyi Wang, Ke Tang, Mamoru Ishii (Purdue Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5193-5203
Investigation of the Mechanisms Which Govern Bubble Geometry in the Spherical Cap Regime Through the Application of Particle Image Velocimetry
Isaiah Wieland, Alexander Dueñas, Wade Marcum, Qiao Wu (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5204-5217
Experimental Study of Flooding Phenomenon in Vertical Annular Smooth and Corrugated Channels
A. Biton (NRCN/Ben-Gurion Univ of the Negev), E. Rabinovich, R. Freud (NRCN), E. Gilad (Ben-Gurion Univ of the Negev)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5218-5229
Prediction of Annular Two-Phase Flow with Heat Transfer
Wenyuan Fan, Haipeng Li, Henryk Anglart (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5230-5238
Analysis of Sensitivity and Uncertainty Quantification for Transient Simulation with the Emphasis on Changes in the Transient Structure
K. Borowiec, C. Pigg, T. Kozlowski (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5239-5252
Uncertainty and Sensitivity Analysis of the PBF SFD Test 1-4 Using MAAP5 Code
Ikuo Kinoshita (Inst of Nuclear Safety System, Inc)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5253-5263
Sensitivity Analysis on the Critical Mass Flowrate Based on Sobol’ Indices Through Replicated LHS
Lucia Sargentini, Guillaume Damblin (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5264-5274
A Best-Estimate-Plus-Uncertainty-Based Method for Design and Design Verification
R. P. Martin (BWX Technol)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5275-5284
Using Deep Learning for the Development of Critical Heat Flux Models for Pressurized Water Reactors
Otto Linsuaín, Boyan D. Ivanov (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5285-5298
A Correlation of the Water Film Thickness and Friction Factor for Supercritical/Subcritical Transition in a Hot-Leg Pipe Geomtery
S. Al Issa, R. Macian-Juan (Technical Univ Munich)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5299-5314
Application of Unstructured Mesh-Based Sodium-Water Reaction Analysis Code SERAPHIM
Akihiro Uchibori, Takashi Takata (JAEA), Yoshimi Shiina, Akira Watanabe (NDD Corp.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5315-5324
Experimental Measurement of Liquid Metal Flow Fields in a Scaled SFR Upper Plenum
Brendan Ward, Broderick Sieh, Hitesh Bindra (Kansas State Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5325-5333
Development of LMFBR System Analysis Code NUSOL-LMR and Analysis of the Transient Accidents in CEFR
Peng Du, Jianqiang Shan, Bo Zhang (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5334-5341
Coupled Neutronics/Thermal Hydraulics Assessment of Graphite Moderated Molten Salt Reactors
A. Nalbandyan, E. B. Klinkby, B. Lauritzen (DTU Nutech), J. Groth Jensen, R. Steyn (Seaborg Technologies)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5342-5355
Experimental Study on the Steam Generator Performance of SMART-ITL Facility
Hwang Bae, Sung-Uk Ryu, Jin-Hwa Yang, Byong Guk Jeon, Yoon Gon Bang, Sung-Jae Yi, Hyun-Sik Park (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5356-5366
Development of a Parametric Computational Fluid Dynamics Model to Estimate Passive Aerosol Decontamination
Rohan M. Biwalkar (Pittsburgh Technical LLC/Carnegie Mellon Univ), Satbir Singh, Nishant Sharma (Carnegie Mellon Univ), Sola M. Talabi (Pittsburgh Technical LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5367-5384
Characterization of Containment Heat Transfer In Nuscale Power Small Modular Reactor (SMR)
Pravin Sawant, Selim Kuran (NuScale Power LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5385-5398
Detailed Measurements of Void-Fraction Distribution in an Adiabatic Fuel Bundle Performed with High Resolution Gamm-Ray Tomography Imaging
Julio Diaz, Robert Adams, Victor Petrov, Annalisa Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5399-5412
Flow Structure in Dead-Ended, Coolant Loop Reactor Branch Lines Related to Thermal Fatigue Onset
J. R. Downing, V. Petrov, A. Manera (Univ of Michigan), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5413-5423
Modal Analysis of Parallel Rectangular Jets Interactions in the RCCS Separate-Effects Test Facility
Daniel Nunez, Benedikt Krohn, Victor Petrov, Annalisa Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5424-5437
Statistical Characterization of Gas-Liquid Flow in Swirl Vane Separator with Image Processing Technique
Li Liu (Jiao Tong Univ/Ji’an Jiaotong Univ), Bofeng Bai (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5438-5448
CFD Prediction of Natural Convection During External Reactor Vessel Cooling
Marco Colombo, Michael Fairweather (Univ of Leeds)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5449-5462
CFD Analysis of the CIGMA Experiments on the Heated Jet Injection into Containment Vessel with External Surface Cooling
A. Hamdani, S. Abe, M. Ishigaki, Y. Sibamoto, T. Yonomoto (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5463-5479
Analysis of Dynamic Natural ConvectionTM Cooling Combined with FLEX Mitigation During Station Blackout Events
Stephen M. Hess, Tom Elicson, Matthew Griffiths (JENSEN HUGHES), Brian Beley, Michael Torcaso, Greg Lazarro (NuVision Eng), Aladar Csontos (EPRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5480-5490
Analysis of Dynamic Natural ConvectionTM Cooling Combined with Accident Tolerant Fuel and FLEX Mitigation During Station Blackout Events
Stephen M. Hess, Tom Elicson, Matthew Griffiths (JENSEN HUGHES), Brian Beley, Michael Torcaso, Greg Lazarro (NuVision Eng), Aladar Csontos (EPRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5491-5502
A Two Phase Mathematical Model to Describe the Dissolution of Corium Crust by Molten Steel
Shambhavi Nandan, Florian Fichot, Fabien Duval (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5503-5517
Experimental Studies on Two-Layer Corium Heat Transfer in Light Water Reactor Lower Head in LIVE2D Facility
X. Gaus-Liu, Th. Cron, B. Fluhrer (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5518-5529
Computational Fluid Dynamics for In-Vessel Retention: Challenges and Achievements
A. Shams, D. Dovizio, K. Zwijsen (NRG), C. Le Guennic (EDF R&D), L. Saas, R. Le Tellier, M. Peybernes, B. Bigot (CEA), E. Skrzypek, M. Skrzypek (NCBJ), L. Vyskocil (UJV Rez a. s.), L. Carenini, F. Fichot (IRSN)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5530-5543
MAAP5 Benchmarking to the TRACE Thermal Hydraulic Tool
Hu Luo, Matthew Griffiths (JENSEN HUGHES), Thomas Kindred, Richard Wachowiak (EPRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5544-5558
MAAP5-VVER Validation and IAEA-SPE-3 Modeling
Tom Elicson, Hugh Luo (JENSEN HUGHES), Lajos Tarczal (Paks Nuclear Power Plant), Tom Kindred, Rick Wachowiak (EPRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5559-5574
The Assessment of the Critical Flow Models of MELCOR2.2 and TRACE V5.0 Against MARVKEN Critical Flow Tests
Pawel Domitr (National Atomic Energy Agency), Piotr Darnowski (Warsaw Univ of Technol), Michal Spirzewski (National Centre for Nuclear Research)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5575-5587
Test Result and MARS-KS Calculation with Uncertainty Propagation Analysis for Pressurizer Surgeline IBLOCA
Byoung-Uhn Bae, Jae-Bong Lee, Yu-Sun Park, Jong-Rok Kim, Seok Cho, Kyoung-Ho Kang (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5588-5598
Development and Assessment of the Thermal Hydraulic System Code ARSAC-K for Analysis of PWR LB LOCA
Mingjun Zhong, Dan Wu, Shuhua Ding, Wei Chen, Yaou Shen, Xiaowei Jiang, Jian Deng (NPIC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5599-5615
Review Paper on Water Film Characteristics
M. Moustafa, T. Ruifeng (Harbin Eng Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5616-5630
Assesment of High Performance Computing for Nuclear Reactor Thermal Hydraulics Applications
Adam Padee, Tomasz Kwiatkowski, Piotr Wasiuk,Tobiasz Jarosiewicz, S?awomir Potempski (National Centre for Nuclear Research), Afaque Shams (NRG)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5631-5638
Dynamics of a Solitary Wire-Wrapped Pin in Axial Flow: A Theoretical Model
C. A. Nixon, W. R. Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5639-5651
Coupled APROS-CFD Simulation of Generic VVER-440 Loss of Feedwater Transient
T. Rämä, T. Toppila, J. Kättö (Fortum Power and Heat), V. Hovi, T. Pättikangas (VTT Technical Research Centre of Finland Ltd)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5652-5666
Thermal-Hydraulic Simulation of Advanced Gas-Cooled Reactors Steam Generators Using Coupled Porous CFD and 1D Two-Phase Flow Modelling
A. Toti, J. Uribe (EDF Energy R&D), M. Rabbitt, C. Sigournay, S. Pandit, P. Brown (EDF Energy Nuclear Generation)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5667-5679
Preliminary Application of the GeN-Foam Multiphysics Tool to the Analysis of the FFTF Sodium Fast Reactor: Coupling Thermal Hydraulics and Core Deformations
Carlo Fiorina, Stefan Radman (EPFL), Andreas Pautz (PSI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5680-5690
Investigation of Subcooled Flow Boiling and CHF on Unoxidized and Oxidized Zircaloy-4 Surfaces
Jee Hyun Seong, Chi Wang, Bren Phillips, Matteo Bucci (MIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5691-5700
X-Ray Radiography for Two-Phase Mixture Level Fluctuation During Boil-Off in Rod Bundle for Wide Pressure Range
T. Arai, M. Furuya, H. Takiguchi, Y. Nishi, K. Shirakawa (CRIEPI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5701-5708
Unexpected Heat Transfer Oscillations in Steady Annular Flow Detected by Synchronized Infrared and Liquid Film Sensor Measurements
G.-Y. Su, B. Phillips, J. Buongiorno (MIT), F. P. D’Aleo, R. M. Streich, H. M. Prasser (ETH Zurich), E. Al-Safran (Kuwait Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5709-5715
CFD and Experiments for Wire-Wrapped Fuel Assemblies
F. Roelofs, H. Uitslag-Doolaard, B. Mikuz, D. Dovizio, D. De Santis, A. Shams (NRG), F. Bertocchi, M. Rohde (TU Delft), KI. Van Tichelen, S. Keijers, G. Kennedy (SCK-CEN), A. Batta, J. Pacio (KIT), P. Planquart (VKI), A. Obabko (ANL) , L. Brockmeyer (ANL/TAMU), Elia Merzari (ANL), R. Vaghetto, Y. Hassan (TAMU), D. Leonard, M. Martin, B. Jackson, M. Steer (Terrapower), M. Delchini, D. Pointer (ORNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5716-5729
A Review of CFD Approaches for Turbulent Mixing Model Development in Subchannel Code
Aiguo Liu, Bao-Wen Yang (Delta Energy Group/Xi’an Jiaotong Univ), Xianlin Zhu (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5730-5751
A Review of Grid Induced Diversion Cross Flow Models in Subchannel Code and the Development
Aiguo Liu (Delta Energy Group), Bao-Wen Yang, (Delta Energy Group/Xi’an Jiaotong Univ), Xianlin Zhu (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5752-5762
A Bundle CHF Mechanism Model and Its Preliminary Verification Under PWR Conditions
Yang Liu, Jianqiang Shan, Bo Zhang (Xi’an Jiaotong Univ), Wei Liu (NPIC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5763-5775
Sensitivity Analysis of Minor Leaks in Light Water Reactor Environments
Lukasz Sokolowski (Kiwa Inspecta Nuclear AB)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5776-5789
Uncertainty Quantification of Thermal-Hydraulic CFD Simulation Using Hybrid Monte-Carlo and Polynomial-Chaos-Expansion Method
D. Gitelman (NRCN/Technion), M. Katz (NRCN),A. N. Shocron, I. Tsarfis, S. Frankel (Technion)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5790-5803
Experiment and Numerical Simulation of a Single Bubble Formation Under a Downward Face of Different Contact Angels
Kai Wang, Nejdet Erkan, Koji Okamoto (Univ of Tokyo)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5804-5815
Bayesian Calibration of Empirical Models Common in MELCOR and Other Nuclear Safety Codes
N. W. Porter, V. A. Mousseau (SNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5816-5826
Overview of Nuclear Reactor Thermal Hydraulic R&D in Xi’an Jiaotong University
G. H. Su, Ronghua Chen (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5827-5839
Design of a Scaled Air Ingress Facility for VHTR Accident Analysis
Z. Welker, A. Manera, V. Petrov (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5840-5847
Numerical Simulation on High Temperature Gas-Cooled Reactors on Less of Coolant Accident
Shuangbao Zhang, Liangxing Li, Wei Xie, Kailin Wang (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5848-5861
Development of Modeling Framework for High-Temperature Heat Pipes in Micro Reactors
Shanbin Shi (RPI), Yang Liu (Virginia Tech), Piyush Sabharwall (INL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5862-5875
Significance of Modeling Specific Geometry in Post-Accident Nuclear Aerosol Transport
Rohan M. Biwalkar, Sola M. Talabi (Pittsburgh Technical LLC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5876-5885
Phenomena Identification and Ranking Table for the eVinciTM Micro Reactor
Richard F. Wright, Andrew M. Dokmanovich (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5886-5893
POD Analysis of the Shell-Side Local Flow in a Five-Rod Helical Coil Steam Generator
Saya Lee, Marilyn Delgado, Yassin A. Hassan (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5894-5904
Artificial Neural Network Method for Automatic Mask Generation for PIV: Applications in a 5x5 Rod Bundle with Mixing Vane Spacer Grids
Gabriel C. Q. Tomaz, Camila F. Matozinhos, Thien Nguyen, Yassin Hassan (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5905-5912
High-Resolution Velocity Measurements in the Vicinity of a Customized Spacer Grid with Rod Bundle Using Matching Index of Refraction and Particle Image Velocimetry
Camila Freitas Matozinhos, Gabriel Caio Queiroz Tomaz, Mason Childs, Thien Nguyen, Yassin Hassan (Texas A&M), Andre A. Campagnole dos Santos (Centro de Desenvolvimento da Tecnologia Nuclear)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5913-5926
Experiment on Density Stratification Behavior by Containment Venting Using CIGMA Facility
Masahiro Ishigaki, Satoshi Abe, Yasuteru Sibamoto, Taisuke Yonomoto (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5927-5940
An Evaluation of External Reactor Vessel Cooling in SMART
Hyung Seok Kang, Donggun Son, Sang Mo An, Rae-Joon Park (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5941-5954
Experimental Study of Natural Convection Heat Transfer Phenomena in a Two-Layer Corium Pools
Yukun Zhou, Yapei Zhang, Zhiyu Yu, Shihao Wu, Wenxi Tian, Suizheng Qiu, G. H. Su, Ronghua Chen, Simiao Tang (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5955-5962
Verification of SAC-3D Based on EBR-II SHRT-45R Benchmark Data
Daogang Lu, Siyu Lyu, Danting Sui (North China Electric Power Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5963-5976
Validation of a Drift-Flux Model Used in the CATHARE Code for Rod Bundle Geometry at Low Pressure and Low Liquid Flow Conditions
T. Lopez, L. Matteo (CEA), Dominique Bestion (Consultant)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5977-5989
Time-Resolved Particle Image Velocimetry Between Two PWR Sub-Bundles
P. M. Bardet (George Washington Univ), F. Bazin, L. Longo, R. Capanna, G. Ricciardt (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5990-5998
Structural and FSI Modeling Approach in Accident Analysis for a Framatome BWR Fuel Design
B. Dressel, Sz.Kovacs (Framatome GmbH), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 5999-6011
A Preliminary Study of Thermal Oscillations Induced by Dryout in Printed Circuit Steam Generator (PCSG)
Jin Su Kwon, Jeong Ik Lee (KAIST), Sang Ji Kim (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6012-6025
Multi-Scale and Multi-Physics Nuclear Reactor Simulation for the Next Generation LWR Safety Analysis
Han Young Yoon, Ik Kyu Park, Jae Ryong Lee, Yunje Cho, Seung-Jun Lee (KAERI), Hyoung Kyu Cho (Seoul Natl Univ), Jae June Jeong (Pusaj National Univ), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6026-6039
Kairos Power Thermal Hydraulics Research and Development
Edward Blandford, Kyle Brumback, Lambert Fick, Craig Gerardi, Brandon Haugh, Elizabeth Hillstrom, Kevin Johnson, Per F. Peterson, Floren Rubio, Fatih S. Sarikurt, Sonat Sen, Haihua Zhao, Nicolas Zweibaum (Kairos Power), invited
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6040-6054
A Two-Phase Flow Model for Use in MAMBA; The CRUD Deposition Code
A. Huxford, V. Petrov, A. Manera (Univ of Michigan)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6055-6068
A Data-Driven Approach to Scale Bridging in System Thermal-Hydraulic Simulation
Han Bao, Robert Youngblood, Hongbin Zhang (INL), Nam T. Dinh, Linyu Lin (NCSU), Jeffrey W. Lane (Zachry Nuclear Eng Inc.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6069-6082
Investigation of Scaling Distortions for NRELAP5 Model of NIST Facility Realized Using the Dynamical Systems Scaling Methodology
Stephen A. Heagy, Cesare Frepoli (FPoliSolutions LLC), Jose N. Reyes (NuScale Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6083-6095
Hot Channel Factor Evaluation for Sodium-Cooled Fast Reactors with Multi-Physics SHARP Toolkit
Yiqi Yu, Emily R. Shemon, Taek K. Kim, Elia Merzari (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6096-6109
Non-Intrusive Two-Phase Flow Regime Identification Method Using FIV and Machine Learning
Shuichiro Miwa, Shuhei Torisaki (Hokkaido Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6110-6116
A Novel Method for Predicting Power Transient CHF via the Heterogeneous Spontaneous Nucleation Trigger Mechanism
Emory Brown, Yikuan Yan, Wade Marcum (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6117-6129
Experimental Characterization of Boiling Two-Phase Flow Structures Under BWR Core Operating Conditions
J.-M. Le Corre (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6130-6148
Modeling Approach of Flowing Condensate Coverage on Inclined Wall for Aerosol Wash Down
Fangnian Wang, Xu Cheng (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6149-6162
CFD Analysis of SETH-2 Test Series Using CUPID Code
Daegwang Hong (KINGS, KEPCO Nuclear Fuel), Donghyun Cho (KINGS, KEPCO E&C), Sang Yong Lee (KINGS), Aya Diab (KINGS, Ain Shams Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6163-6175
Post-Test Calibration of the Effective Momentum Source (EMS) Model for Steam Injection Through Multi-Hole Spargers
Xicheng Wang (KTH/Tsinghua Univ), Ignacio Gallego Marcos, Dmitry Grishchenko, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6176-6189
Pre-Test Analysis for HYMERES-2 PANDA Tests Series for Steam Injection into Pool Through Spargers
Xicheng Wang (KTH/Tsinghua Univ), Ignacio Gallego Marcos, Dmitry Grishchenko, Pavel Kudinov (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6190-6203
Quantification of Uncertainty in Pressure Loss Associated with Manufacturing Tolerances in Nuclear Fuel Assemblies
George Bache (Framatome), Klaus Vogel (Framatome GmbH), Benjamin Farges (Framatome SAS), Lise Charlot (Framatome)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6204-6216
Uncertainty Quantification on SAM Simulations of EBR-II Loss-of-Flow Tests
Travis Mui (Univ of Illinois/ANL), Rui Hu, Guanheng Zhang (ANL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6217-6229
Comparison of Random and Deterministic Sampling Methods for Quantification of the Input Uncertainty in CFD
A. Cutrono Rakhimov D. C. Visser, E. M. J. Komen (NRG)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6230-6243
Model and Boundary Uncertainty Analysis of PWR LBLOCA Transient Event in RELAP5/MOD3.3 Code
Chih-Chia Chiang, Hao-Chun Chang (Natl Tsing Hua Univ), Jong-Rong Wang, Chunkuan Shih (Nuclear and New Energy Education and Research Foundation), Shao-Wen Chen, Yu-Ming Feng (Natl Tsing Hua Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6244-6256
Four Field Flow Modeling of Forced Convective Boiling
T. D. Strayer, G. M. Burdick, R. W. Dacus, T. Gallaway, B. L. Magolan, B. M. Waite (NNL)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6257-6270
Development of the CATHARE 3 Three-Field Model for Simulations in Large Diameter Horizontal Pipes
Philippe Fillion (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6271-6282
Current Intergroup Mass Transfer Limitations in the Multi-Group Two-Fluid Model
Longxiang Zhu (Univ of Illinois/Xi’an Jiaotong Univ), Zhiee Jhia Ooi, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6283-6295
Validation of Interfacial Area Concentration Approaches for Prediction of Gas-Dispersed Condensing Flows
Vineet Kumar, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6296-6308
Visualization Experiment for Convective Heat Transfer in a Rectangular Riser of Air-Cooled Reactor Cavity Cooling System
Sin-Yeob Kim , Goon-Cherl Park, Hyoung Kyu Cho (Seoul Natl Univ), Chan Soo Kim (KAERI), Goon-Cherl Park, Hyoung Kyu Cho (Seoul Natl Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6309-6322
Improvement of GAMMA+ for Turbulent Mixed Convection of Air in a Vertical Duct of Reactor Cavity Cooling System
Dong-Ho Shin, Sin-Yeob Kim, Goon-Cheryl Park, Hyoung Kyu Cho (Seoul Natl Univ), Chan Soo Kim (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6323-6334
CFD Assessment of LOFA Intra Core Natural Circulation in the High Temperature Test Facility
Izabela Gutowska, Brian G. Woods (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6335-6348
Simultaneous Measurements of Temperature and Velocity by Optical Methods in Mixing Jets
Mira Chitt, David Guenadou, Lionel Rossi (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6349-6356
TDLAS Diagnostic for Investigation of Steam Ingress Accident in HTGRs
Michael C. Button, Philippe M. Bardet (George Washington Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6357-6364
Experimental Investigation on Turbulence Flow Downstream a Spacer Grid with Split-Type Mixing Vanes in a 5x5 Rod Bundle Using PIV
Wenhai Qu, Jinbiao Xiong, Xu Cheng (Shanghai Jiao Tong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6365-6387
Development of Aqueous Molecular Tagging Velocimetry to Measure Wall Shear Stress
C. Fort, M. A. André, P. M. Bardet (George Washington Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6388-6394
MAAP5 Passive Containment Cooling System Model for Korean Advanced Power Reactor Plus
Byung Jo Kim, Jeongseong Lee, Kyubok Lee (KEPCO E&C), Paul McMinn, Chan Y. Paik (Fauske & Associates, LLC), Thomas Kindred (EPRI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6395-6408
Mapping Emergency Cooling Water Spray System Test Results to the AP1000® PWR Spent Fuel Pool Physical Layout
Robert N. Pinkston (Westinghouse)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6409-6417
Performance Analysis of External Drywell Cooling on BWR Mark II Drywell Head During a Short-Term Station Blackout Scenario by MELCOR
Miao Gui, Jun Wang, Ryan Dailey, Michael L. Corradini (Univ of Wisconsin, Madison)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6418-6429
Two-Phase Flow Structure in a Particle Bed Packed in a Confined Channel
Daisuke Ito, Tatsuya Kurisaki, Kei Ito, Yasushi Saito (Kyoto Univ), Yuya Imaizumi, Ken-ichi Matsuba, Kenji Kamiyama (JAEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6430-6439
MELCOR and ASTEC Validation on Prelude Test
J. Duspiva, M. Kotou? (UJV Rez)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6440-6453
Assessment of Empirical Models and Uncertainty and Sensitivity Study of a High-Velocity Steam Condensation Experiment with TRACE
W. Jaeger, W. Hering (KIT)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6454-6467
Condensation Heat Transfer of the Steam-Air Mixture on Bundle Heat Exchanger of PCCS (Passive Containment Cooling System)
Byoung-Uhn Bae, Seok Kim, Yu-Sun Park, Kyoung-Ho Kang (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6468-6476
Study of the Thermal-Hydraulic Behaviors of an Open-Loop PCCS
Xianmao Wang (China Nuclear Power Technol Research Inst), Jun Wang (Univ of Wisconsin, Madison), Suizheng Qiu (Xi’an Jiaotong Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6477-6487
Development of a Component-Based Scaling Methodology for Fluoride-Salt-Cooled High-Temperature Reactors
Ishak Johnson, Per Peterson (Univ of California, Berkeley)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6488-6501
Numerical Verification of the Kairos Power Systems Code KP-SAM
Lambert H. Fick, Haihua Zhao (Kairos Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6502-6515
Scaling Methodology for Integral Effects Tests in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology
Nicolas Zweibaum, Edward Blandford, Craig Gerardi, Per Peterson (Kairos Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6516-6535
Overview of Kairos Power Systems Code KP-SAM Development
Haihua Zhao, Lambert Fick, Justin Herter, Brandon Haugh (Kairos Power)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6536-6550
A Mechanistic Spray Model for Lumped Parameter Reactor Containment Modeling
D. Bestion (Consultant), T. Lopez (CEA)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6551-6563
Development and First Validation of the Tailored CFD Solver ‘ContainmentFoam’ for Analysis of Containment Atmosphere Mixing
S. Kelm, M. Kampili (FzJ), G. Vijaya Kumar (FzJ/ Indian Inst of Technol Madras), Kinshiro Sakamoto (FzJ/Fukui Univ), X. Liu, C. Druska, A. Kuhr (FzJ), K. Arul Prakash (Indian Inst of Technol Madras), H.-J. Allelein (FzJ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6564-6578
Improvement of Physical Modeling for Coupled Heat and Mass Transfer in a Square Cavity with Condensation in the Presence of Non-Condensable Gas
Nan Jiang, Etienne Studer (DEN/STMF, CEA, Université Paris-Saclay), Bérengère Podvin (LIMSI, CNRS, Université Paris-Saclay)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6579-6592
Mesh Sensitivity Analysis of 1-D Nuclear System Analysis Code with Higher-Order Numerical Scheme
Wonwoong Lee, Jae Jun Lee, Sung Gil Shin, Jeong Ik Lee (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6593-6603
Comparisons of Friction Models Implemented in U.S. TRACE and Korean MARS-KS System TH Codes
Sung Gil Shin, Jeong Ik Lee (KAIST)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6604-6617
Development of a Droplet Entrainment Correlation for a Vertical Upward Annular-Mist Flow
Jee Min Yoo, Kum Ho Han, Jae Jun Jeong (Pusan National Univ), Han Young Yoon (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6618-6631
Study on Evaluation Method for Entrained Gas Flow Rate by Free Surface Vortex
Kei Ito, Daisuke Ito, Yasushi Saito (Kyoto Univ), Toshiki Ezure, Kentarou Matsushita, Masaaki Tanaka (JAEA), Yasutomo Imai (NDD Corp.)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6632-6642
Validation of the Interfacial Area Transport Equation Coupled with the Void Transport Equation for Prediction of Flashing Flows
Zhiee Jhia Ooi, Vineet Kumar, Caleb S. Brooks (Univ of Illinois)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6643-6654
Discrete Element Modeling of Conduction Cool Down in Pebble-Bed Reactors Under Loss of Forced Convection
Dan Gould (General Atomics-ASI), Mary Ross, Hitesh Bindra (Kansas State Univ)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6655-6668
Velocimetry/Thermometry Data Fusion from DCC Tests in the HTTF
M. A. André, P. M. Bardet (George Washington Univ), S. R. Cadell, B. Woods (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6669-6678
Standard Fuel Block Test to Validate Core Thermo-Fluid Analysis Code for Prismatic Gas-Cooled Reactor
Chan Soo Kim, Byung Ha Park, Eung Seon Kim (KAERI)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6679-6689
LOCA-Type Scenario Simulation for NuScale-SMR with RELAP/SCDAPSIM/MOD3.4
Katarzyna Skolik (AGH Univ of Science and Technology), , Anuj Trivedi, Marina Perez-Ferragut, Chris Allison (Innovative Systems Software)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6690-6700
Validation of the Trace Code Against Small Modular Integral Reactor Natural Circulation Phenomena
F. Mascari (ENEA), B. G. Woods (OSU), K. Welter (NuScale Power), F. D’Auria (Univ of Pisa)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6701-6714
Scaling Effects of Film Flow Regimes in SMR Integral Tests
Dongyoung Lee, Qiao Wu (OSU)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6715-6726
Surface Characteristics of Accident Tolerant Fuels Cladding and Their Potential Impact in Critical Heat Flux
Rajnikant Umretiya, Daniel Ginestro, Sama Bilbao y Leon, Jessika Rojas (Virginia Commonwealth Univ), Barret Elward, Mark Anderson (Univ of Wisconsin, Madison), Raul B. Rebak (GE Global Research)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6727-6740
A Study on Safety Margin of In-Vessel Melt Retention for VVER1000 Reactor
Long Manh Doan, Tran Chi Thanh (Viet Nam Atomic Energy Inst), Nguyen Van Thai (Hamoi Univ of Science and Technology)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6741-6754
Analytical Transient Two-Phase Model for Dry-Superheated Debris Bed Under Top Flooding Conditions
Alejandro Villarreal Larrauri, Renaud Meignen (IRSN), Michel Gradeck, Nicolas Rimbert (LEMTA CNRS, Univ of Lorraine)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6755-6769
Development of Surrogate Model for Debris Bed Coolability Analysis
Yangli Chen, Weimin Ma (KTH)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6770-6779
Force Balance Model Assessment for Mechanistic Prediction of Sliding Bubble Velocity in Vertical Subcooled Boiling Flow
Junsoo Yoo (INL), Yassin A. Hassan (Texas A&M)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6780-6793
TRACE High Pressure Condensation Model Validation Using KAIST Data
J. Thompson, P. Lien (NRC)
Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 6794-6807

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019)

Portland, OR, August 18-23