Table of Contents
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Monday, August 31, 2015
1:30-3:35 p.m.
Track 7: Investigation of Reflood Phenomena in Partially Blocked Core with Fuel Relocation
Session Organizer: Elia Merzari (ANL)
1 The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident
Georges Repetto, Cristina Dominguez, Benoit Durville, Sebastien Carnemolla (Institut de Radioprotection et de Surete Nucleaire), Nicolas Tardif (LGCIE INSA Lyon), Damien Campello (LaMCoS-INSA Lyon), Michel Gradeck (Laboratoire d’Energétique et de Mécanique Théorique et Appliquée)
15 Experimental Study for Effects of Ballooning and Power Peak on a Coolability of Fuel Rod Bundle
Jongrok Kim, Sang-Ki Moon, Jongrok-Kuk Park, Chul-Hwa Song (KAERI)
24 Core Coolability in Loss of Coolant Accident: The COAL Experiments
Georges Repetto, Christophe Marquie, Benoit Bruyere, Tony Glantz (Institut de Radioprotection et de Surete Nucleaire)
38 Extended Study of Coolability of VVER Bundle with Ballooned Region
Imre Nagy, Zoltán Hózer, Tamás Novotny, Péter Windberg, András Vimi (Hungarian Academy of Sciences)
Track 7: Thermal Hydraulic Experiments and Numerical Analysis in Support of MYRRHA—I
Session Organizer: Elia Merzari (ANL)
47 Thermal-Hydraulic Study of the LBE-Cooled Fuel Assembly in the MYRRHA Reactor: Experiments and Simulations
Julio Pacio (KIT), Heleen Doolaard, Ferry Roelofs (NRG), Katrien Van Tichelen (SCK/CEN), Thomas Wetzel (KIT)
61 Experimental Investigation of the Pressure Loss Characteristics of the Full-Scale MYRRHA Fuel Bundle in the COMPLOT LBE Facility
Graham Kennedy, Katrien Van Tichelen (SCK/CEN), Heleen Doolaard (NRG)
74 Fuel Pin Bundle Experimental Characterization in HLM Large Pool System
Daniele Martelli (Univ of Pisa), Mariano Tarantino (ENEA), Nicola Forgione (Univ of Pisa), Ivan Di Piazza (ENEA), Gianluca Barone, Morena Angelucci (Univ of Pisa), Pietro Agostini (ENEA)
86 CFD Pre-Test Analysis of the Fuel Pin Bundle Simulator Experiment in the NACIE-UP HLM Facility
Ivan Di Piazza (ENEA Brasimone R.C.), Ranieri Marinari (Univ of Pisa)
101 Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility
Ivan Di Piazza (ENEA Brasimone R.C.), Morena Angelucci, Nicola Forgione (Univ of Pisa), Giuseppe Polazzi, Valerio Sermenghi, Mariano Tarantino, Daniel Giannotti, Lorenzo Laffi, Stefano Cati (ENEA)
Track 7: Advances in Enhancement, Understanding and Prediction of CHF and Quenching—I
Session Organizer: Elia Merzari (ANL)
113 Development of CHF Mapping Method for Fin Structured Surface
Jinyoung Choi, Hee C. No (KAIST)
127 Effects of Various Thin Film Coating Techniques on Pool Boiling Heat Transfer
Gwang Hyeok Seo, Hong Hyun Son, Uiju Jeong, Gyoodong Jeun, Sung Joong Kim (Hanyang Univ)
139 Effect of Oxide Layer Thickness on the Pool Boiling Critical Heat Flux of Pre-Oxidized RPV Material
Hong Hyun Son, Uiju Jeong, Gwang Hyeok Seo, Gyoodong Jeon, Sung Joong Kim (Hanyang Univ)
153 Effects of Coating Structure by Al2 O3 Nanoparticles Deposition on Critical Heat Flux of R123 in Flow Boiling
Seok Bin Seo, In Cheol Bang (UNIST)
166 Quenching Performance in Nanofluids and Nanoparticles-Deposited Surfaces
Kyung Mo Kim, In Cheol Bang (UNIST)
Track 4: Addressing Scaling Issues
Session Organizer: Elia Merzari (ANL)
177 The Dynamical System Scaling Methodology
Jose N. Reyes, Jr. (NuScale Power LLC)
192 The Dynamical System Scaling Methodology: Comparing Dimensionless Governing Equations with the H2TS and FSA Methodologies
Jose N. Reyes, Jr. (NuScale Power LLC), Cesare Frepoli (FPoliSolutions LLC), Joseph P. Yurko (NuScale Power LLC)
207 Scaling Analysis for DVI Line Break Accident of APR1400 based on ATLAS Experiment
Erol Bicer, Alin Tatu (KEPCO International Nuclear Graduate School), Heeran Ko (Korea Hydro & Nuclear Power Co., LTD), Taewan Kim (KEPCO International Nuclear Graduate School)
217 Core Exit Temperature Response during an SBLOCA Event in the Ascó NPP
Jordi Freixa, Víctor Martínez-Quiroga, Francesc Reventós (Technical Univ of Catalonia)
231 Analysis of Kv in Power-to-Volume Scaling. Application to a SBLOCA Transient
Andrea Querol Vives, Sergio Gallardo, Gumersindo Verdu (Univ Politècnica de València)
Track 2: Computational Fluid Dynamics—I
Session Organizer: Si Young Lee (SRNL)
245 Large Eddy Simulation of Non-Isothermal Turbulent Flow Past a Circular Cylinder
Sasan Salkhordeh (Univ of Pittsburgh), Anirban Jana (Pittsburgh Supercomputing Center), Mark L. Kimber (Univ of Pittsburgh)
252 Overview of the TRIOCFD Code: Main Features, V&V Procedures and Typical Applications to Nuclear Engineering
Pierre-Emmanuel Angeli, Ulrich Bieder, Gauthier Fauchet (CEA)
266 Wall Resolved Large Eddy Simulation of a Flow Through a Square-Edged Orifice in a Round Pipe at RE=25000
Sofiane Benhamadouche, Wadih James Maalouf, Mario Arenas (EDF R&D)
280 Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives
Elia Merzari, Paul Fischer, Andrew Siegel, Justin Walker, Yiqi Yu, Noah Halford (ANL)
298 Modeling of Fluctuating Fluid Forces Exerted on the Walls of a Concentric Annular Pipe Using Large Eddy Simulation
Saptarshi Bhattacharjee (CEA/Aix-Marseille Univ), Guillaume Ricciardi (CEA), Stephane Viazzo (Aix-Marseille Univ)
Track 3: CHF and Post CHF Heat Transfer, Flooding and CCFL
Session Organizer: Elia Merzari (ANL)
311 ORFEOTM—A CHF Correlation Form Applied to GAIA, AREVA’s Advanced PWR Fuel Assembly Design
Ole Wieckhorst (AREVA GmbH), Richard L. Harne, Mihnea S. Anghelescu (AREVA Inc.), Harry Gabriel (AREVA GmbH), Olivier Martinie (AREVA SAS)
324 COBRA-TF Evaluation and Application for PWR Steamline Break DNB Analysis
Yixing Sung, Vefa Kucukboyaci, Liping Cao (Westinghouse), Robert Keith Salko (ORNL)
338 Study on Critical Heat Flux with Non-Uniform Axial Heat Flux Distributions During Lifetime in Reactor Core
Dawei Zhao, Wenxing Liu, Yuanfeng Zan, Wanyu Xiong, Zumao Yang (RETH, Nuclear Power Inst of China)
352 A Validation of Westinghouse Mechanistic and Empirical Dryout Prediction Methods Under Realistic BWR Transient Conditions
Oscar Puebla Garcia (Deloitte Consulting S.L.), Jean-Marie Le Corre (Westinghouse Electric Sweden)
365 An Updated Approach to the Prediction of Dryout and Void Fraction for RBWR Bundles
Xingang Zhao, Koroush Shirvan, Yingwei Wu, Mujid S. Kazimi (MIT Univ)
Track 1: Interfacial Area Transport (Data Base, Modeling, Measurement Techniques)
Session Organizer: Yang Liu (Virginia Polytech Inst & State Univ)
379 CFD Prediction of Subcooled Boiling with Advanced Mechanistic Models of Interfacial Area Transport Equation
V. T. Nguyen (Hanoi Univ of Science and Technology), C.-H. Song (KAERI), C. T. Tran (Vietnam Atomic Energy Inst)
389 Evaluation of Interfacial Area Transport Equation in Coupled Two-Fluid Model Computation
J. P. Schlegel (Missouri Univ Sci Tech), T. Hibiki (Purdue Univ), X. Shen (Kyoto Univ), S. Appathurai, H. Subramani (Chevron Energy Technology Co.)
403 Interfacial Area Density Measurement using a Three-Layer Wire-Mesh Sensor
H.-M. Prasser, S. Stucki, (ETH Zurich), T. Betschart (Paul Scherrer Inst), J. Eisenberg (ETH Zurich)
419 Statistical Characteristics of Free Falling Water Film
A. A. Nikoglou, E. P. Hinis, S. E. Simopoulos (National Technical Univ of Athens)
433 Evaluating Performance of Two Group Interfacial Area Transport Equation for Large Diameter Pipes
A. Dave, A. Manera (Univ of Michigan), M. Beyer, D. Lucas (Helmholtz-Zentrum Dresden-Rossendorf)
Track 5: Modeling and Experiments of Severe Accidents—I
Session Organizer: Elia Merzari (ANL)
446 Melcor Analysis of Early Containment Venting Risk in a Severe Accident Scenario of Boiling Water Reactor
Huimin Zhang, Zheng Huang, Weimin Ma (KTH)
458 Development of an In-Vessel Severe Accident Analysis Code MIDAC
Longze Li, Yapei Zhang, Wenxi Tian, G. H. Su, Suizheng Qiu (Xi’an Jiaotong Univ)
471 Phenomenological Modeling Approach to Anisotropic Ablation in Molten Core Concrete Interactions
Kyoungmin Kang, Michael L. Corradini (Univ of Wisconsin, Madison)
484 Melt-Concrete Interface Heat Transfer Models and Coolability Models: KWU PWR Analyses with MELCOR/CORCON and CORQUENCH
Adolf Rydl, Bernd Jaeckel (Paul Scherrer Inst), Jens-Uwe Kluegel, Pascal Steiner (Kernkraftwerk Goesgen)
Track 1: Fundamental Thermal-Hydraulic: General—I
Session Organizer: Elia Merzari (ANL)
499 Numerical Studies of O2 Leak Modeling in Sodium-CO2 Heat Exchanger in the SFR Coupled with the S-CO2 Brayton Cycle
Hwa-Young Jung, Jeong Ik Lee (KAIST), Myung-Hwan Wi (KAERI)
508 Numerical Modeling of the Two-Phase Underexpanded Reactive CO2 -into-Sodium Jets in the Frame of Sodium Nuclear Fast Reactors
Daniele Vivaldi (CEA), Frederic Gruy (Ecole Nationale Supérieure des Mines de Saint Etienne), Christophe Perrais (CEA)
520 Development and Verification of Behavior of Tritium Analytic Code (BOTANIC)
Min Young Park, Eung Soo (Seoul Natl Univ)
533 Development of a Mechanistic Evaluation Method for Wastage Environment Under Sodium-Water Reaction Accident
Akihiro Uchibori, Hiroyuki Ohshima (JAEA)
545 Effects of Surface Orientation on Wall Heat Flux Partitioning During Nucleate Pool Boiling of Saturated Water at Atmospheric Pressure
Satbyoul Jung, Hyungdae Kim (Kyung Hee Univ)
Track 4: NPP Transient and Accident Analysis—I
Session Organizer: Elia Merzari (ANL)
559 TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5
Lap-Yan Cheng (BNL), Peter Yarsky (NRC), Joo Seok Baek, Arantxa Cuadra, Arnold Aronson, David Diamond (BNL)
575 Use of White Noise in TRACE/PARCS Analysis of ATWS with Instability
Tarek Zaki, Peter Yarsky (NRC)
587 Axial Conduction Nodalization for TRACE/PARCS Analysis of ATWS with Instability Peter Yarsky, Matthew Hardgrove (NRC)
Peter Yarsky, Matthew Hardgrove (NRC)
597 Sensitivity to TMIN in TRACE/PARCS Analysis of ATWS with Instability
Peter Yarsky (NRC)
611 Control Rod Drop Transient: Uncertainty and Sensitivity Analysis of Thermal-Hydraulic Variables using a 3D Model with TRACE V5.0P3/PARCS 3.0
Carles Mesado Melia, Marina Garcia Fenoll, Rafael Miro Herrero (ISIRYM), Gumersindo Verdu (UPV)
Monday, August 31, 2015
4:00-6:30 p.m.
Track 7: CFD Benchmark of NESTOR High Fidelity PWR Rod Bundle Data at In-Core Conditions
Session Organizer: Elia Merzari (ANL)
627 Overview of CFD Round Robin Benchmark of the High Fidelity Fuel Rod Bundle NESTOR Experimental Data
Daniel M. Wells (EPRI), Pierre Peturaud (Independent Contractor), Suresh Kumar Yagnik (EPRI)
640 Application of CD-ADAPCO Best Practices to NESTOR OMEGA MVG Benchmark Exercises Using STAR-CCM+
Eric Volpenhein, Robert Brewster (CD-Adapco), Emilio Baglietto (MIT), Cassandra Carpenter (CD-Adapco), Jeffry Smith (Toyota Racing Development)
653 Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark
Mathieu G. Martin, Thomas Keheley (AREVA Inc), Klaus Vogel, Kevin Goodheart (AREVA GmbH), Anca Hatman (AREVA Inc), Alexandre Chatelain (AREVA NP SAS)
667 Westinghouse CFD Modeling and Results for EPRI NESTOR CFD Round Robin Exercise of PWR Rod Bundle Testing
Michael E. Conner, Zeses Karoutas, Yiban Xu (Westinghouse)
679 Pressure Drop Predictions Using Code_Saturne in NESTOR CFD Benchmark
Sofiane Benhamadouche (EdF R&D)
692 CFD Methodologies for a PWR Fuel Rod Assembly
Ted Blowe, Shin Kyu Kang, Yassin Hassan (Texas A&M)
Track 7: Hydrogen Management after Fukushima—I
Session Organizer: Elia Merzari (ANL)
711 Hydrogen Management Strategies and Analysis Codes Implemented by the OECD Member Countries
Zhe Liang (Canadian Nuclear Laboratories), Martin Sonnenkalb (Gesellschaft für Anlagen- und Reaktorsicherheit), Ahmed Bentaib (Institut de Radioprotection et de Sûreté Nucléaire), Marco Sangiorgi (EC JRC)
724 Hydrogen Risk Assessment—CFD Model Validation and Reactor Scale Application
D. C. Visser, N. B. Siccama, E. M. J. Komen (NRG), T. L. J. Keij, J. G. T. te Lintelo (EPZ)
737 Hydrogen Combustion Benchmark Using Experiment in Double-Compartment Experimental Vessel
Giovanni Manzini (RSE SpA), Ivo Kljenak (Jozef Stefan Inst), Lubica Kubisova (Nuclear Regulatory Authority of the Slovak Republic), Mantas Povilaitis (Lithuanian Energy Inst)
749 Validation of Two Turbulent Flame-Speed Closure Models for Slow and Fast Hydrogen Deflagration
Tadej Holler (Jožef Stefan Inst), Varun Jain, Ed M. J. Komen (Nuclear Research and Consultancy Group)
761 Operational Experience of Ceramic Honeycomb Passive Autocatalytic Recombiner as a Hydrogen Mitigation System
Chang-Hyun Kim, Je-Joong Sung, Sang-Jun Ha (KHNP), Phil-Won Seo (Ceeracomb, Co., Ltd.)
771 Validation and Application of the REKO-DIREKT Code for the Simulation of Passive Auto-Catalytic Recombiners (PARs) Operational Behavior
Ernst-Arndt Reinecke, S. Kelm (FzJ), M. Klauck (RWTH Aachen Univ), P.-M. Steffen (FzJ), H.-J. Allelein (RWTH Aachen Univ)
Track 1: Experimental Measurement Techniques and Flow Visualization—I
Session Organizer: Philippe M Bardet (The George Washington Univ)
785 Investigations on Centrifugal Pumps under Air Entrainment Conditions
Thomas Schäfer, André Bieberle, Uwe Hampel (HZDR)
797 Study of Two-Phase Pipe Flow using the Axial Wire-Mesh Sensor
Arto Ylonen, Juhani Hyvarinen (Lappeenranta Univ of Technology)
807 Measurement of Wall Temperature Fluctuations During Thermal Mixing of Non-Isothermal Water Streams
Henryk Anglart, Mattia Bergagio, Stellan Hedberg, Stefan Rydstrom (KTH), Wiktor Frid (Swedish Radiation Safety Authority)
819 Distributed Temperature Sensor Testing in Liquid Sodium
Craig D. Gerardi, Nathan Bremer, Darius D. Lisowski, Stephen W. Lomperski (ANL)
829 Tomographic Reconstructions and Predictions of Radial Void Distribution in BWR Fuel Bundle with Part-Length Rods
Magnus Ahnesjö, Peter Andersson (Uppsala Univ), Jean-Marie Le Corre, Stig Andersson (Westinghouse Electric Sweden)
841 Mesh Sensor for High Temperature High Pressure Applications
John Kickhofel, Horst-Michael Prasser (ETHZ), Karthick Selvam, Eckhart Laurien, Hermann Huber (Univ of Stuttgart)
Track 2: Multiscale Multiphysics Applications in Thermal Hydraulics—I
Session Organizer: R. Brian Jackson (TerraPower)
854 Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment
Santosh Bhatt (Areva Inc.), John Jones, Ryan Swanson, Stephen Palzewicz (AREVA Inc.), Lanfranco Monti (AREVA NP SAS), Galina Sieber (AREVA GmbH)
868 Comparison of Overlapping and Separate Domain Coupling Methods
Timothy Paul Grunloh, Annalisa Manera (Univ of Michigan)
882 Multi-Scale Thermal-Hydraulic Analysis of Safety Systems of Advanced PWRs using the CUPID Code
Han Young Yoon (KAERI), Hyoung Kyu Cho (Seoul Natl Univ), Jae Jun Jeong (Pusan National Uniy), Chul-Hwa Song, Ik Kyu Park (KAERI)
896 Towards a Coupled Simulation of Thermal Hydraulics and Neutronics in a Simplified PWR with a 3x3 Pin Assembly
Anni Schulze, Hans-Josef (RWTH Aachen Univ), Stephan Kelm (FzJ)
908 Analysis of Improved Fuel Rod Modeling in Coupled Thermal-Hydraulics/Neutronics Calculations
Ana Jambrina Gomez, Mine Yilmaz, Maria N. Avramova, Kostadin N. Ivanov (Penn State)
926 A Control Theory Approach to Adaptive Stepsize Selection for Coupled CFD and CRUD Chemistry Simulations
Daniel J. Walter, Victor Petrov, Annalisa Manera (Univ of Michigan), Brian Kendrick (LANL)
Track 2: Computational Fluid Dynamics—II
Session Organizer: Si Young Lee (SRNL)
940 Phase-Field Modeling of Binary Eutectic Alloy Solidification With Convection
Stefan Meyer, Ivan Otic, Xu Cheng (KIT)
952 Assessment of OpenFOAM CFD Toolbox for Gravity driven Turbulent Mixing Flows in a Reactor Pressure Vessel
Riccardo Puragliesi (Scherrer Inst), Qing Zhou (CEA), Omar Zerkak, Andreas Pautz (Scherrer Inst)
966 Validation of CFD-Codes for Natural Convection and Condensation Phenomena in Containments with German THAI-Experiments
Joern Stewering, Berthold Schramm, Martin Sonnenkalb (Gesellschaft fuer Anlagen- und Reaktorsicherheit)
979 Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD
Muthanna H. Al Dahhan (Missouri Univ of Science and Technology), P. Jain (ORNL), S. Usman (Missouri Univ of Science and Technology), Rizwan Uddin (Univ of Illinois), I. A. Said (Missouri Univ of Science and Technology), M. M. Kao (Univ of Illinois), M. M. Taha (Missouri Univ of Science and Technology)
996 Thermal-Hydraulic Design and CFD Analysis of Fuel Assembly for China Lead-Based Research Reactor
Tao Zhou, Zengfang Ge, Shuyong Liu, Yunqing Bai, Yong Song (Chinese Academy of Sciences)
1006 Numerical Analysis of Core Thermal-Hydraulic for Sodium-Cooled Fast Reactors
Alain Conti, Antoine Gerschenfeld, Yannick Gorsse, Thierry Cadiou, Romain LaVastre (CEA)
Track 6: Thermal Hydraulics in Sodium-Cooled Fast Reactors (General)—I
Session Organizer: W. David Pointer (ORNL)
1020 Liquid Metal Heat Transfer Under Low Peclet Number Conditions
Hiroyasu Mochizuki (Univ of Fukui)
1033 Experimental Study of Gas Entrainment from Surface Swirl
Brahim Moudjed, Lionel Rossi, Roland Riva, Jacques Excoffon (CEA)
1041 Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO
Kunihiko Nabeshima, Norihiro Doda, Takero Mori, Hiroaki Ohira, Hiroyuki Ohshima (JAEA), Takashi Iwasaki (NESI Inc.)
1050 Development of Optical Fiber Instrumentation for use in Sodium Cooled Fast Reactors Matthew
T. Weathered, Mark Anderson (Univ of Wisconsin, Madison)
1060 Numerical Analyses on the Safety Aspects of KASOLA Test Facility
Hristo V. Hristov, Thorsten Hollands (GRS), Maxime Haselbauer, Wadim Jaeger, Wolfgang Hering (KIT)
Track 1: Two-Phase Flow and Heat Transfer Fundamentals—I
Session Organizer: Seungjin Kim (Penn State)
1074 Thermal Hydraulics Analysis for Cooling Tower Performance
Si Young Lee, Alfred J. Garrett (SRNL)
1088 Transient Convective Boiling: Analysis of Experimental Results
Nicolas Baudin (IRSN), Catherine Colin (IMFT), Pierre Ruyer (IRSN), Julien Sebilleau (IMFT)
1102 Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel
Liqin Zhang, Yanping Huang, Mingliang Song, Yuanfeng Zan, Junfeng Wang, Yanlin Wang (Nuclear Power Inst of China)
1116 Experimental and Analytical Study of Flashing Flow Through Steam Generator Tube Cracks
Shripad T. Revankar (Purdue Univ), Jovica R. Riznic (Canadian Nucl Safety Comm)
1130 Development and Validation of A New Drift Flux Model in Rod Bundle Geometries
Ikuo Kinoshita, Toshihide Torige (Inst of Nulcear Safety System, Inc.), Minoru Yamada (MHI Nuclear Eng Co.,Ltd.), Takashi Hibiki (Purdue Univ)
1143 Uncertainty Analysis of Delayed Equilibrium Model (DEM) using the CIRCE Methodology
Jean-Marie Seynhaeve (UCLouvain), Agnes De Crecy (CEA), Yann Bartosiewicz (UCLouvain)
Track 5: Severe Accidents: General
Session Organizer: Elia Merzari (ANL)
1157 First Results of the Simulation of the Fukushima-Daiichi Unit 3 Accident for an Assessment of the Applicability and Capability of the Code ATHLET-CD
Christoph Bratfisch, Mathias Hoffmann, Marco K. Koch (RUB)
1170 PHEBUS FPT-1 Simulation, using MELCOR: Blockage Model Analysis
Jun Wang, Michael L. Corradini, Troy C. Haskin (Univ of Wisconsin, Madison)
1183 Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits during BWR Station Blackout Accidents
Kevin R. Robb (ORNL)
1196 Determination of In-Vessel Retention under Molten Corium Pool Attack
D. Home, M. Chai (AMEC Foster Wheeler)
1210 Effect of Particle Spreading on Coolability of Ex-Vessel Debris Bed
S. E. Yakush (Russian Academy of Sciences), A. Konovalenko, S. Basso, P. Kudinov (KTH)
Track 3: Computational Fluid Dynamics V&V—I
Session Organizer: Elia Merzari (ANL)
1223 Large-Eddy Simulation of Thermal Striping in PLAJEST Experiment with Trio U
Pierre-Emmanuel Angeli (CEA)
1237 CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel
Fatih Sinan Sarikurt, Yassin A. Hassan (Texas A&M)
1251 Analysis of Panda Spray Experiments Performed in Two Interconnected Vessels with OpenFOAM
Nejdet Erkan, Koji Okamoto (Univ of Tokyo)
1261 Transient Convection from Forced to Natural with Flow Reversal for CFD Validation
Blake W. Lance, Barton L. Smith (Utah State Univ)
1275 CFD and Experimental Analysis of Single Phase Buoyancy Driven Counter-Current Flow in a Pipe
Frederic Sebilleau, Raad Issa, Simon P. Walker (Imperial College London), Anuj Kumar Kansal, Naresh Kumar Maheshwari (BARC)
Track 2: Core Thermal Hydraulics and Subchannel Analysis
Session Organizer: David L. Aumiller (BAPL)
1289 Hot Fuel Element Thermal-Hydraulic Modeling in the Jules Horowitz Reactor Nominal and LOFA Conditions
Reijo Pegonen, Henryk Anglart (KTH Royal Inst of Technology), Serge Bourdon, Christian Gonnier (CEA, DEN, DER, SRJH)
1303 Determination of the Pressure Loss Coefficient at the Control-Rod Guide Tube Flow-Hole for a PWR Nuclear Fuel Assembly by using CFD and Bernoulli Solutions
Dong-Yuan Sheng (Westinghouse Electric Sweden AB), Marcus Seidl (E.ON Kernkraft GmbH)
1316 Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor
Abhijit Pandurang Deokule (Homi Bhabha National Inst), Alok Kumar Vishnoi, Arnab Dasgupta, Umasankari Kannan, Dinesh Chandraker, Pallipatu Krishnan Vijayan (BARC)
1324 Evaluation of 1-D Void and Pressure Drop Models over a Wide Range of Fuel Bundle Geometries and Operating Conditions
Manuel Auliano (Norwegian Univ Sci Tech), Jean-Marie Le Corre (Westinghouse Electric Sweden)
1338 On the Analytical Solutions and Numerical Verifications of Two-Phase Water Faucet Problem
Ling Zou, Haihua Zhao, Hongbin Zhang (INL)
1352 Development of Burnup Dependent Fuel Rod Model in CTF
Mine Ozdemir Yilmaz, Maria N. Avramova (Penn State)
Tuesday, September 1, 2015
8:00-9:00 a.m.
Tuesday Keynote Session—I
1366 Nuclear Safety and Thermal Hydraulics: Personal Thoughts and Some Recent Progress
George Yadigaroglu (ETH-Zurich), D. Lakehal (ASCOMP AG)
Tuesday Keynote Session—II
1379 Thermal Hydraulics in FHRS: Key Similarities and Differences with LWRS
Per F. Peterson (Univ of California, Berkeley)
Tuesday Keynote Session—III
1380 On the Use of (U)RANS and LES Approaches for Turbulent Incompressible Single Phase Flows in Nuclear Engineering Applications
S. Benhamadouche (EdF R&D)
Tuesday, September 1, 2015
9:30 a.m.-12:00 p.m.
Track 7: NEAMS Sponsored Advances in Thermal Hydraulics Modeling and Simulation
Session Organizer: Justin W. Thomas (ANL)
1394 URANS Simulations of Thermal Stratification in a Large Enclosure for Severe Accident Scenarios
L. B. Carasik (Texas A&M), F. Sebilleau, S. P. Walker (Imperial College London), Y. A. Hassan (Texas A&M)
1408 A High-Order System Thermal-Hydraulics Model for Advanced Reactor Safety Analyses
Rui Hu (ANL)
1422 Coupled Calculations of SAS4A/SASSYS-1 and STAR-CCM+ for the SHRT-45R Test in EBR-II
Klaus Huber (KIT), Justin W. Thomas (ANL)
1435 Steady and Unsteady Calculations on Thermal Striping Phenomena in Triple-Parallel Jet
Y. Q, Yu, E. Merzari, J. W. Thomas, A, Obabko (ANL)
1448 Erosion of a Large-Scale Gaseous Stratified Layer by a Turbulent Round Jet S—Simulations with URANS and LES Approaches
A. Kraus, S. Aithal, A. Obabko, E. Merzari (ANL), A. Tomboulides (Western Macedonia Univ), Paul Fischer (Univ of Illinois)
1462 Verification and Validation of Nek5000 for T-Junction, Matis , SIBERIA, and Max Experiments
Aleksandr Obabko (ANL), Paul Fischer (ANL/Univ of Illinois), Oana Marin, Elia Merzari (ANL), Dave Pointer (ORNL)
Track 7: Hydrogen Management after Fukushima—II
Session Organizer: Elia Merzari (ANL)
1474 Simulation of Hydrogen Distribution in the Containment during a Severe Accident with Fast Hydrogen-Steam Release
D. Papini, M. Andreani, B. Ničeno, H.-M. Prasser (Paul Scherrer Institut), P. Steiner, J.-U. Klügel (Kernkraftwerk Gösgen-Däniken AG)
1488 Re-Evaluation of PAR Concept in German PWR with Revised PAR Model
M. Sonnenkalb, S. Band, H. Nowack, S. Schwarz (GRS mbH)
1502 Combined Effects of Cooler and Spray Activation on the Hydrogen Distribution in the Presence of a Jet Flow
D. Paladino, R. Kapulla, G. Mignot, S. Paranajpe (PSI)
1516 A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)
Ernst-Arndt Reinecke (FzJ), Ahmed Bentaib (IRSN), Jürgen Dornseiffer (FzJ), Daniel Heidelberg (RWTH Aachen Univ), Frank Morfin (CNRS), Pascal Zavaleta (IRSN), Hans-Josef Allelein (RWTH Aachen Univ/FzJ)
1530 Hydrogen Safety: Laminar and Turbulent Flame Speed of Spherical Flame in a Fan-Stirred Closed Vessel
J. Goulier, N. Chaumeix (CNRS/ICARE), N. Meynet, A. Bentaïb (IRSN)
1540 Passive Autocatalytic Recombiners (PAR) Induced Ignition and the Resulting Hydrogen Deflagration Behaviour in LWR Containments
Sanjeev Gupta, Teja Kanzleiter, Gerhard Poss (Becker Technol GmbH)
Track 1: Experimental Measurement Techniques and Flow Visualization—II
Session Organizer: Philippe M. Bardet (The George Washington Univ)
1554 Computational Fluid Dynamics Modeling and Validation of Swirling Flow in a Pipe with Classic Twisted Tape
Minseop Song, So Hyun Park, Eung Soo Kim (Seoul Natl Univ)
1566 Flow Characterization within a Sphere-Packed Bed using PIV Measurement
Z. J. Hong, L. Xiong, N.X. Wang, W. Zhou (Chinese Academy of Sciences)
1573 System Analysis and Isothermal Separate Effect Experiments of the Accident Behavior in PWR Spent Fuel Storage Pools
H. Chahi, W. Käestner, S. Alt (Univ of Applied Sciences Zittau/Görlitz)
1587 Local Parameters of Air-Water Two-Phase Flow at a Vertical T-Junction
G. Monrós-Andreu, R. Martinez-Cuenca, S. Torró, S. Chiva (Univ Jaume I)
1601 A Separate-Effect Test Facility for CFD-Grade Measurements of the RCCS Upper Plenum
Thien Nguyen, Victor Petrov, Annalisa Manera (Univ of Michigan)
1615 High Resolution Experiments of Velocity and Concentration Fluctuations in a Jet Flow
Victor Petrov, Thien Duy Nguyen, Daniel Nunez, Dave Akshay, Annalisa Manera (Univ of Michigan)
Track 7: Issues and Advances in Thermal Hydraulic Research of FHRs
Session Organizer: Elia Merzari (ANL)
1629 Development of the FHR Advanced Natural Circulation Analysis (FANCY) Code
Z. Guo, N. Zweibaum (Univ of California, Berkeley), M. Shao (LBNL), L. R. Huddar, P. F. Peterson (Univ of California, Berkeley), S. Qiu (Xi’an Jiaotong Univ)
1645 Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility
Q. Lv, H. C. Lin, X. Sun, R. N. Christensen, T. E. Blue (Ohio State), G. Yoder, D. Wilson (ORNL), P. Sabharwall (INL)
1659 Experimental Strategy for the Determination of Heat Transfer Coefficients in Pebble-Beds Cooled by Fluoride Salts
L. Huddar, P. F. Peterson (Univ of California, Berkeley), R. O. Scarlat (Univ of Wisconsin, Madison), Z. Guo (Xi’ian Jiaotong Univ/Univ of California, Berkeley)
1676 Thermal Analysis of Pebble-Bed Reactors based on a Tightly Coupled Mechanical-Thermal Model
Yanheng Li, Wei Ji (RPI)
1688 Design, Fabrication and Startup Testing in the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology
N. Zweibaum, J. E. Bickel, Z. Guo, J. C. Kendrick, P. F. Peterson (Univ of California, Berkeley)
1704 Validation of Best Estimate Models for Fluoride-Salt-Cooled, High-Temperature Reactors Using Data from the Compact Integral Effects Test (CIET 1.0) Facility
N. Zweibaum, Z. Guo (Univ of California/Xi’an Jiaotong Univ), L. R. Huddar, P. F. Peterson (Univ of California, Berkeley)
Track 2: Containment Analysis (with V&V)
Session Organizer: Marco Pellegrini (Inst of Applied Energy)
1716 Nuclear Reactor Containment Flows—Modelling of Stably Stratified Layer Erosion by a Turbulent Jet
L. Ishay, G. Ziskind (Ben-Gurion Univ of the Negev), U. Bieder (CEA), A. Rashkovan (NRCN)
1730 Containment Analysis of Fukushima Daiichi Unit 1 Power Station using GOTHIC
O. E. Ozdemir, T. L. George, M. Marshall (Zachry Nuclear Engineering, Inc.)
1744 Study of the Influence of the Design Parameters and Initial Condition of Passive Containment Cooling System
Yan Wang, Yaoli Zhang, Zhiwei Zhou (Tsinghua Univ), Yanning Yang (State Nuclear Power Technology Research and Development Centre)
1758 A Lumped Parameter Modeling for Mixing and Stratification in a BWR Mark I Pressure Suppression Pool
O. E. Ozdemir, T. L. George (Zachry Nuclear Eng, Inc.)
1773 Evaluation of Passive Containment Cooling with an Advanced Water Film Model in a Lumped-Parameter Code
Xi Huang, Xu Cheng (KIT), Walter Klein-Hessling (GRS)
1787 Synthesis of the OECD/NEA-PSI CFD Benchmark Exercise
M. Andreani, A. Badillo, R. Kapulla, B. Smith (PSI)
Track 7: Passive Safety System and Accidents Measures
Session Organizer: Elia Merzari (ANL)
1802 Using NASA’s GFSSP Code for Steady State and Transient Modeling of Gas Cooled Reactor Passive Safety Systems
Wesley C. Williams (Louisiana State Univ), Jeffrey McLean (CDI Corp.)
1811 Feasibility Study of Hybrid Heat Pipe with Control Rod as Passive In-Core Cooling System for Advanced Nuclear Power Plant
Yeong Shin Jeong, Kyung Mo Kim, In Guk Kim, In Cheol Bang (UNIST)
1821 Optimization Methodology for Large Scale Fin Geometry on the Steel Containment of a Public Acceptable Simple SMR (PASS)
Do Yun Kim, Hee Cheon No, Ho Sik Kim (KAIST)
1835 Preliminary Design of the I2 S-LWR Containment System
Mingjun Wang (Xi’an Jiaotong Univ/Univ of Michigan), Annalisa Manera (Univ of Michigan), Matthew J. Memmott (Brigham Young Univ), John C. Lee (Univ of Michigan), Suizheng Qiu (Xi’an Jiaotong Univ)
1848 Experimental Study and Validation of MARS Code for CCFL in Passive Emergency Core Cooling System (PECCS) of Public Acceptable Simple SMR (PASS) System
Ho Sik Kim, Mun Won Song, Hee Cheon No (KAIST)
1858 Heat Removal Capacity of Heat Pipe Designs for In-Core Passive Decay Heat Removal System
Kyung Mo Kim, In Guk Kim, Yeong Shin Jeong, , In Cheol Bang (UNIST)
Track 1: Two-Phase Flow and Heat Transfer Fundamentals—II
Session Organizer: Annalisa Manera (Univ of Michigan)
1870 Rayleigh-Taylor Instability of Viscous Flow with Heat and Mass Transfer
Byoung Jae Kim, Kyung Doo Kim (KAERI)
1879 Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel
Y. Sato, J. Takeuchi (MHI), D. Komiyama, Y. Uno (Mitsubishi Nuclear Fuel Co., Ltd.), R. A. Fortman, G. I. Hadaller (Stern Laboratories Inc.)
1888 Measurements of the Vertical Distribution of the Void Fraction using X-ray Attenuation for Different Flow Regimes in a Horizontal Pipe
L. Rossi, R. De Fayard, S. Kassab (CEA)
1900 An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region
Peng Zhang, Peipei Chen, Wei Li, Zhi Di, Lei Zhang, Xiao Hu, Yaheng Zou, Zhi Di (SNPTC)
1913 Thermal-Hydraulic Study of Siphon Breaking Phenomenon on a Two-Phase Gas/Liquid Flow
P.-A. Douxchamps, C. Diakodimitris, C. Mandy, C. Angulo (Tractebel Eng)
1924 Experimental Investigation of the High Performance Steam Injector Operation
Shuichiro Miwa, Yuto Takeya, Hiroto Endo, Michitsugu Mori (Hokkaido Univ)
Track 2: Computational Multi-Fluid Dynamics—I
Session Organizer: Emilio Baglietto (MIT)
1939 Numerical Modeling of Horizontal Annular Flows using a Droplet Entrainment Model
Thomas Hoehne (HZDR)
1952 Progress on Computation of Boiling Flow in Fuel Assemblies with NEPTUNE_CFD
Cyril Baudry, Nicolas Merigoux, Jerome Lavieville, Stephane Mimouni, Mathieu Guingo (EdF)
1966 Modeling of Two-Phase Flow in a BWR Fuel Assembly with a Highly-Scalable CFD Code
Adrian Tentner, Prasad Vegendla, Aleks Obabko, Oana Marin, Elia Merzari (ANL)
1980 Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows
Dirk Lucas, E. Krepper, R. Rzehak, Y. Liao, T. Ma, T. Ziegenhein (HZDR)
1992 A Novel Approach for Turbulence Modeling of Wavy Stratified Two-Phase Flow
Matthias Benz, Thomas Schulenberg (KIT)
Track 3: Computational Fluid Dynamics V&V—II
Session Organizer: Elia Merzari (ANL)
2006 Validation of ANSYS CFX for Gas and Liquid Metal Flows with Conjugate Heat Transfer Within the European Project THINS
A. Aleksandrov Papukchiev, S. Buchholz (GRS mbH)
2020 The Development of Surface Vortices in Strongly Rotating Flow in a Cylindrical Vessel: Numerical Simulation
F. Bloemeling (TUEV NORD Nuclear), S. Richter, M. Schlueter (Hamburg Univ of Technology)
2034 A Methodology for Characterizing Representativeness in Power Plant Performance Indicator Measurements with CFD Simulations
U. Otgonbaatar, E. Baglietto, N. Todreas (MIT)
2048 Tailored Experiments for Validation of CFD with FSI for Nuclear Applications
Eric Lillberg, Kristian Angele, Gustav Lundqvist (Vattenfall AB), Nicholas Edh (Forsmarks Kraftgrupp AB)
2059 Software Quality Assurance and V&V Procedure During the Development Stages of EdF CFD Tool Code_SATURNE: Focus on Verification Tests
J. Fontaine, M. Ferrand, E. Le Coupanec (EdF)
2073 On the Liquid Metal Heat Transfer in Annular Channels: Review, Proposal and Validation of Empirical Models
W. Jaeger, W. Hering, M. Lux (KIT)
Track 3: Plant System Code Validation—I
Session Organizer: Elia Merzari (ANL)
2087 Assessment Study of RELAP5/SCDAP Capability to Reproduce Liquid Metal Tall Facility Thermal Hydraulic Behaviour
F. Fiori, Z. W. Zhou (Tsinghua Univ)
2103 Validation of CATHARE Code on the 3D ROSA-LSTF Pressure Vessel
S. Carnevali, P. Bazin (CEA)
2117 Recommendations of Two-Phase Critical Non-Flashing Flow Mixture Calculations in One-Dimensional System Code RELAP5
Lukasz Sokolowski (Inspecta Nuclear AB), Tomasz Kozlowski (Univ of Illinois)
2131 Comparison of MARS-KS to COBRA-TF for Models and Correlations in Pre-CHF Regime
Min-Gil Kim, Wonwoong Lee, Jeong Ik Lee (KAIST), Young Seok Bang (KINS)
2143 Preliminary Results of a Comparative Assessment of ATHLET-CD and MELCOR by Simulating the Experiment PHEBUS FPT1
Christian Bratfisch, Marco K. Koch (Ruhr-Univ Bochum)
2157 Towards a Consolidated Approach for the Validation of Plant System Codes and Models: Case Study for a BWR Fast Depressurization Event
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi (PSI)
Tuesday, September 1, 2015
1:30 -3:35 p.m.
Special session: Celebrating Mujid Kazimi’s Legacy: 40 Years of Innovation in Nuclear Engineering
2171 Development of a Societal-Risk Goal for Nuclear Power Safety
Caleb Roh, Vicki Bier, Michael Corradini, Shuji Liu (Univ of Wisconsin, Madison), Robert Youngblood (INL), Gregory Hammond (AFIT)
Track 7: Thermal Hydraulic Experiments and Numerical Analysis in Support of MYRRHA—II
Session Organizer: Elia Merzari (ANL)
2182 Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor
Chiara Spaccapaniccia, Philippe Planquart, Jean-Marie Buchlin (von Karman Inst), Matteo Greco, Fabio Mirelli, Katrien Van Tichelen (SCK/CEN)
2196 CFD Benchmark for a Heavy Liquid Metal Fuel Assembly
H. J. Doolaard, A. Shams, F. Roelofs (NRG), K. Van Tichelen, S. Keijers (SCK/CEN), J. De Ridder, J. Degroote, J. Vierendeels (Ghent Univ), I. Di Piazza, R. Marinari (ENEA), E. Merzari, A. Obabko, P. Fischer (ANL)
2209 Tracking of Fuel Particles After Pin Failure in Nominal, Loss-of-Flow and Shutdown Conditions in the MYRRHA Reactor
S. Buckingham, P. Planquart (von Karman Inst), K. Van Tichelen (SCK/CEN)
2223 Pre-Test Computational Fluid Dynamics and System Thermal Hydraulics Calculations of The E-SCAPE Scaled LBE Pool Facility
M. Greco, F. Mirelli, S. Keijers, K. Van Tichelen (SCK/CEN)
2237 MyrrhaFoam: A CFD Model for the Study of the Thermal Hydraulic Behavior of MYRRHA
Lilla Koloszar, Sophia Buckingham (Von Karman Inst), Steven Keijers (SCK/CEN) Wang, S. He (The Univ of Sheffield)
Track 7: Advances in Enhancement, Understanding and Prediction of CHF and Quenching—II
Session Organizer: Elia Merzari (ANL)
2251 Research on Flow Characteristics for the Optimal Design of Experiment for the Typical Pressured Water Reactor
G. L. Chen, Z. J. Zhang, Z. F. Tian, X. M. Dong (Harbin Engineering Univ)
2261 Critical Heat Flux Enhancement Mechanism by Surface Modification based on Hydrodynamic Instability Mode
Han Seo, In Cheol Bang (UNIST)
2268 Trend Analysis for Low Pressure Low Flow Tube CHF
Xirui Liu, Bao-Wen Yang, Yudong Zha (Xi’an Jiaotong Univ)
2279 Development of a Mechanistic Critical Heat Flux Correlation
Jeffrey Luitjens, Qiao Wu (Oregon State Univ)
Track 7: Heat Transfer in Supercritical Flows
Session Organizer: Elia Merzari (ANL)
2293 Fluid-Structure Interaction in a Wire-Wrapped Rod Bundle Cooled with Supercritical Water
D. C. Visser, A. Shams, V. R. Bhimanadam (NRG)
2301 Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study
V. Valori, G. E. Elsinga, M. Rohde, M. J. Tummers, J. Westerweel, T. H. J. J. van der Hagen (TU Delft)
2315 Development and Validation of a Scaling Method for Supercritical Fluid Heat Transfer
X. J. Liu, X. Cheng (Shanghai Jiao Tong Univ)
2324 Experimental Study on the CO2 to Water Heat Exchanger Performance Near the CO2 Critical Point
Yoonhan Ahn, Seungjoon Baik, Jeong Ik Lee (KAIST)
2334 Direct Numerical Simulation of Fluid Flow at Supercritical Pressure in a Vertical Channel
W Wang, S. He (Univ o/Sheffield)
Track 7: Realistic BWR LOCA Evaluation: Methodology Development and Application
Session Organizer: Elia Merzari (ANL)
2348 BWR-4 LOCA Modeling with RELAP5
K. Nikitin, P. Mueller, J. Martin, W. van Doesburg (BKW Energie AG), D. Hiltbrand (Studsvik)
2362 RELAP5 BWR-4 Model Development and Validation for NPP Mühleberg (KKM)
P. Mueller, K. Nikitin, W. van Doesburg (BKW Energie AG), D. Hiltbrand (Studsvik)
2375 KKM TRACG LOCA
Samuel Lafountain, Baris Sarikaya, Jordan Hagaman, Phil Sharpe, Dan Pappone, Kurshad Muftuoglu (GE Hitachi), Willem van Doesburg, Konstantin Nikitin (BKW)
2389 KKM TRACG Validation
Samuel Lafountain, Baris Sarikaya (GE Hitachi), Willem van Doesburg, Konstantin Nikitin (BKW)
2398 TRACG Application on BWR/2 LOCA
G. Li, L. Klebanov, P. Sharpe, K. Muftuoglu, C. Heck (GE Hitachi)
Track 6: Thermal Hydraulics in Small Modular Reactors—I
Session Organizer: Elia Merzari (ANL)
2413 Ocean-Based Passive Decay Heat Removal in the Offshore Floating Nuclear Plant (OFNP)
J. Zhang, J. Buongiorno, M. Golay, N. Todreas (MIT)
2427 Study of Safety and International Development of Small Modular Reactors (SMR)
S. Buchholz, A.- K. Kruessenberg, A. Schaffrath (GRS GmbH)
2441 Experimental Research on Non-Condensable Gases Effects in Passive Decay Heat Removal System
Liu Yang, Jia Hai-jun (Tsinghua Univ)
2452 Compact Steam Generator for Nuclear Application
G. Haratyk, K. Shirvan, M. S. Kazimi (MIT)
2466 Passive Decay Heat Removal Capability of Fixed Bed Nuclear Reactor Fuel Chamber
Muhammad Rizaal, Koji Okamoto, Nejdet Erkhan (Univ of Tokyo)
Track 4: BEPU Analysis and Challenges in Licensing
Session Organizer: Elia Merzari (ANL)
2477 Non-Parametric Order Statistics: Providing Assurance of Nuclear Safety
M. A. Shockling (Westinghouse)
2491 Reevaluation of Station Blackout Risk of OPR-1000 Nuclear Power Plant Applying Combined Approach of Deterministic and Probabilistic Method
Dong Gu Kang, Seung-Hoon Ahn (KINS)
2503 10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs
Cesare Frepoli, Joseph P. Yurko (FPoliSolutions LLC), Ronaldo H. Szilard, Curtis L. Smith, Robert Youngblood (INL)
2517 Sampling Variance and Bias of Wilks’ Conservative Estimate of Confidence Intervals
J. P. Hessling (SP Technical Research Inst of Sweden), P. Hedberg (Swedish Radiation Safety Authority)
2531 Uncertainty and Sensitivity Analysis of the OECD/NEA KALININ-3 Benchmark
I. Pasichnyk (GRS GmbH), S. Nikonov (VNIIAES), W. Zwermann, K. Velkov (GRS GmbH)
Track 5: Modeling and Experiments of Severe Accidents—II
Session Organizer: Elia Merzari (ANL)
2541 Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario
P. Drai, P. Chatelard, L. Laborde, L. Piar, F. Fichot, G. Brillant (IRSN)
2557 Enhancements in MAAP5.03+ MCCI and Corium Coolability Models and Benchmarks against OECD CCI Tests
Quan Zhou, Chan Y. Paik, Paul B. McMinn (Fauske & Associates, LLC)
2571 Effects of Porous Superhydrophilic Surfaces on Flow Boiling Critical Heat Flux in IVR Accident Scenarios
Reza Azizian, Thomas McKrell, Kresna Atkhen (EdF), Jacopo Buongiorno (MIT)
2584 Thermal Effects of Material Discontinuities and Oxidation on Graphite Matrix in HTGRs
Dan Gould, Hanwen Liu, Hitesh Bindra (Kansas State Univ)
2598 Simulation of LIVE-L4 with ATHLET-CD
T. Hollands, C. Bals (GRS)
Track 3: Computational Fluid Dynamics V&V—III
Session Organizer: Bao-Wen Yang (Xi’an Jiaotong Univ)
2611 CFD Analysis of Non-Axial Flow in Fuel Assemblies
U. BIeder (CEA)
2624 Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks
N. Mérigoux, J. Laviéville, S. Mimouni, M. Guingo, C. Baudry, S. Bellet (EdF)
2644 Multiphase RANS Simulations of Turbulent Bubbly Flows
M. Colombo, M. Fairweather (Univ of Leeds), S. Lo, A. Splawski (CD-adapco)
2658 Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes
Rui Zhang, Wenwen Zhang, Tenglong Cong, Wenxi Tian, G. H. Su, Suizheng Qiu (Xi’an Jioatong Univ)
2673 Verification of Interface-Tracking Method with Manufactured Solution
Kei Ito, Hiroyuki Ohshima (JAEA), Tomoaki Kunugi (Kyoto Univ)
Track 4: NPP Transient and Accident Analysis—II
Session Organizer: Elia Merzari (ANL)
2684 Analysis of LOCA Scenarios in the NIST Research Reactor Before and After Fuel Conversion
Joo Seok Baek, Lap-Yan Cheng, David Diamond (BNL)
2699 OSCARD Coupling Software for Main Steam Line Break Fault Analysis—Assessment of the Mixing Phenomena in the Vessel
Jérémie Galarin, Hugues Neyret-Duperray, Ouardia Touazi, Simon Pelissier (EdF)
2712 Comparison of Thermal Hydraulic Analysis Methods (Codes) for the University of Florida Training Reactor (UFTR)
D. Springfels, K. A. Jordan, D. Schubring (Univ of Florida)
2725 Conclusions on Boron Precipitation following a Large Break Loss of Coolant Accident
K. Umminger, B. Schoen, S. P. Schollenberger (AREVA GmbH)
2735 Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems
Zijiang Yang, Xiaofei Xiong, Junli Gou, Jianqiang Shan, Guomin Zhang, Li Ge (Xi’an Jiaotong Univ)
Tuesday, September 1, 2015
4:00-6:30 p.m.
Track 7: CFD Modeling of Fuel Assemblies: From High Fidelity to Low Resolution Models
Session Organizer: Elia Merzari (ANL)
2747 CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies
Eugeny Sosnovsky (Varian Medical Systems), Emilio Baglietto (MIT), Steven Keijers, Katrien van Tichelen (SCK/CEN), Thiago Cardoso de Souza, Heleen Doolaard, Ferry Roelofs (NRG)
2762 Analysis of Pressure Drop in Rod Bundles in Heavy Liquid Metal
A. Batta, A. Class (KIT)
2774 Calibration of High Fidelity Bare Rod Bundle Simulations for Various Prandtl Fluids
T. Cardoso de Souza, A. Shams, F. Roelofs (NRG), T. Kwiatkowski (National Center for Nuclear Research)
2788 Investigating Reactor Components with the Coarse-Grid-Methodology
M. Viellieber A. Class (IKET)
2802 Scaling Considerations About LWR Core Thermal Hydraulics
D. Bestion, L. Matteo (CEA)
2817 High-Fidelity Numerical Reference Simulation of the Flow Through an Infinite Wire-Wrapped Assembly
A. Shams, F. Roelofs, E. M. J. Komen (NRG)
Track 7: Modelings and Experiments of IVR and Core Catcher Strategies
Session Organizer: Elia Merzari (ANL)
2830 Detailed Analysis of Geometry Effect on Two Phase Natural Circulation Flow under IVR-ERVC
R. Park, K. S. Ha, H. Y. Kim (KAERI)
2844 Analysis of APR1400 Core Degradation under Cavity-Flooded Condition using MELCOR
Kukhee Lim, Yongjin Cho (KINS)
2857 Effect of Wettability and Two-Phase Flow Conditions on Flow Boiling CHF Enhancement for Slug Flow
Hae Min Park, Yong Hoon Jeong (KAIST)
2871 Heat Removal Characteristics of IVR-ERVC Cooling System Using Gallium Liquid Metal
Seong Dae Park, Hyo Heo, In Cheol Bang (UNIST)
2881 CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions
Dong Hoon Kam, Hae Min Park, Young Jae Choi, Yong Hoon Jeong (KAIST)
Track 2: Multiscale Multiphysics Applications in Thermal Hydraulic—II
Session Organizer: Brian Jackson (Oregon State Univ)
2892 Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator Driven Sub-Critical System
Gang Wang, Zhen Wang, Ming Jin, Yunqing Bai, Yong Song (Chinese Academy of Sciences)
2903 Testing Coupled MCNP6/CTF on an Assembly Level Problem with an Acceleration Technique
A. Bennett, K. Ivanov, M. Avramova (PSU)
2917 Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility
A. Papukchiev (GRS GmbH), C. Geffray (Technische Univ Muenchen), M. Jeltsov, K. Kööp, P. Kudinov, D. Grischenko (KTH)
2931 Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS
Brendan Kouchunas, Thomas J. Downar, Dan Jabaay (Univ of Michigan), Benjamin Collins, Shane Stimpson, Andrew Godfrey, Kang Seog Kim, Jess Gehin (ORNL), Scott Palmtag (Core Physics Inc.), Fausto Franceschini (Westinghouse)
2945 Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository
N. Lubchenko, E. A. Bates, E. Baglietto, M. J. Driscoll, M. Rodriguez-Buño (MIT), R. Podgorney (INL)
Track 1: Subchannel Fluid Dynamics and Heat Transfer
Session Organizer: Hisashi Ninokata (Politecnico di Milano)
2958 Numerical Investigation of Buoyancy-Aided Flow in Rod-to-Wall Gap Regions
Y. Duan, S. He (Univ of Sheffield)
2972 RANS Simulation of Turbulent Swept Flow over a Wire in a Channel for Core Thermal Hydraulic Design
Byung-Hyun You, Yong Hoon Jeong (KAIST), Yacine Addad (Khalifa Univ)
2984 Experimental and Computational Study of Ribbed Cladding for PWR Rod Bundles Heat Transfer Enhancement
L. A. Carrilho, M. B. Dzodzo (Westinghouse), J. A. Khan (Univ of South Carolina)
3005 High Resolution Thermal Mixing at Westinghouse ODEN Loop
L. David Smith III, Paul F. Joffre (Westinghouse), Jean-Marie Le Corre, Fredrik Waldemarsson, Anders Hallehn, Henrik Tejne (Westinghouse Electric Co. Sweden AB)
3017 An Initial Uncertainty Analysis on the Critical Heat Flux Evaluation for a Small-Scale Pressurized Nuclear Reactor using the COBRA Code
J. P. Duarte, J. R. C. Piqueira (Univ of São Paulo), P. F. Frutuoso e. Melo (Federal Univ of Rio de Janeiro)
Track 6: Thermal Hydraulics in Sodium-Cooled Fast Reactors (Transient Models and Validation)—II
Session Organizer: Elia Merzari (ANL)
3030 EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2
L. Briggs (ANL), S. Monti (IAEA), W. Hu (China Inst of Atomic Energy), D. Sui (North China Electric Power Unit), G. H. Su (Xi’an Jiatong Univ), L. Maas (Inst for Radiological Protection and Nuclear Safety), B. Vezzoni (KIT), U. Partha Sarathy (IGCAR), A. Del Nevo (ENEA), A. Petruzzi (Nuclear and Industrial Eng.), R. Zanino (Politecnico di Torino), H. Ohira (JAEA), H. Mochizuki (RINE), K. Morita (Kyushu Univ)
3044 Simulations of the EBR-II Tests SHRT-17 and SHRT-45R
T. Sumner, A. Moisseytsev (ANL)
3058 Transient Analysis of the ASTRID Demonstrator Including a Gas Nitrogen Power Conversion System with the CATHARE2 Code
F. Bertrand, G. Mauger (CEA)
3071 Qualification of a RELAP5-3D© System Code Nodalization of EBR-II
A. Del Nevo (ENEA), E. Martelli (Univ of Rome “La Sapienza”)
3085 Computational Thermal Hydraulics Schemes for SFR Transients Studies
Marie-Sophie Chenaud, L. I. Simon, Marine Anderhuber, Laura Matteo, Antoine Gerschenfeld (CEA)
Track 1: Two-Phase Flow and Heat Transfer Fundamentals—III
Session Organizer: Seungjin Kim (Penn State)
3099 Numerical Prediction of Turbulent Convective Heat Transfer with Molten Salt in Circular Pipe
Yushuang Chen, Zhongfeng Tang, Naxiu Wang (Chinese Academy of Science)
3111 Experimental Study of Heat Transfer Mechanisms Under Exponential Power Excursion in Plate-Type Fuel
G. Su (MIT), M. Bucci (CEA), T. J. Mckrell , J. Buongiorno, (MIT)
3124 Experimental Investigation of Critical Heat Flux for Zero and Natural Circulation Flow of Water in Three Rods Bundle near Atmospheric Pressure
Y. Aharon, I. Hochbaum (NRCN)
3134 Numerical Investigations of a Spent Fuel Storage Pool in Abnormal Conditions
J.-P. Simoneau, B. Gaudron, Jérôme Laviéville, Julien Dumazet (EdF)
3148 Thermal Shrinkage Based Model for Predicting the Voids during Solidification of Lead
Niranjan Gudibande, Kannan Iyer, (Indian Inst of Technology)
3162 Experimental Investigation of Thermal Hydraulic Limits of BWR RCIC System Operation under Long-Term Operation
M. Solom, K. Vierow (Texas A&M), A. Nosek (NRC)
Track 2: Computational Multi-Fluid Dynamics—II
Session Organizer: Emilio Baglietto (MIT)
3176 Numerical Study of Direct Contact Condensation of Steam on Stable Interface in a BWR Supression Pool Test Facility
G. Patel, V. Tanskanen, V. Rintala, J. Hyvärinen (Lappeenranta Univ of Technology)
3190 Momentum Convection within the Staggered Grid Formulation
J. W. Lane, T. L. George (Zachry Nuclear Eng, Inc.)
3204 Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model
S. L. Sharma, T. Hibiki, M. Ishii (Purdue Univ), J. P. Schlegel (Missouri Univ Sci and Technology), J. R. Buchanan, Jr., K. J. Hogan (Bechtel Marine Propulsion Corp.), P. W. Guilbert (ANSYS UK Ltd)
3218 A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle
T. Strömgren, A. Zhezherun, Y. Le Moigne, J.-M. Le Corre, D. Y. Sheng, S. Perzon (Westinghouse Electric Sweden)
3231 Modeling of Interfacial Momentum Exchange for Wall-Bounded Bubbly Flows
Jungwoo Kim (Seoul National Univ of Science and Technology) Donjoo Kim (Kumoh National Inst of Technology), Hyungmin Park, Jun Ho Lee (Seoul Natl Univ)
3240 Modeling of Rayleigh-Taylor Instability for Steam Direct Contact Condensation
Marco Pellegrini, Masanori Naitoh (The Inst of Applied Energy), Colin Josey, Emilio Baglietto (MIT)
Track 5: Debris Bed Cooling
Session Organizer: Elia Merzari (ANL)
3255 Experimental Investigations on the Coolability of Debris Beds under Variation of Inflow Conditions
S. Leininger, R. Kulenovic, E. Laurien (Univ of Stuttgart)
3269 Unsteady Void Measurements Within Debris Beds using High Speed X-Ray Tomography
E. Laurien, T. Stürzel, M. Zhou (Univ of Stuttgart)
3279 Validation of the MEWA Code Against POMECO-HT Experiments and Coolability Analysis of Stratified Debris Beds
Zheng Huang, Weimin Ma, Sachin Thakre (KTH)
3292 Experimental Study of Pressure Drops in Coarse Particle Beds,
R. Clavier, N. Chikhi, F. Fichot (IRSN), M. Quintard (IMFT)
3306 An Experimental Study on Flow Characteristics of Homogeneous and Stratified Debris Beds
Liangxing Li, Xumao Zou, Jiaojiao Lou, Huixiong Li, Xianliang Lei (Xi’an Jiaotong Univ)
3318 First Experimental Results of Large Scale Debris Bed Reflood Tests in the PEARL Facility
Nourdine Chikhi, T. Garcin, F. Foubert, P. March, F. Fichot (IRSN)
Track 3: Plant System Code Validation—II
Session Organizer: Xiaodong Sun (Ohio State)
3336 On the Definition of a Minimum Set of Requirements to Assess the Adequacy of the RELAP5-3D Multidimensional Flow Capability with Selected Canonical Problems
C. Frepoli, J. W. Fricano, J. P. Yurko (FPoliSolutions LLC), F. Buschman, D. Aumiller (BAPL)
3351 Simulation of Faraday Waves with RELAP5-3D Thermal-Hydraulic Code
C. Frepoli, J. W. Fricano (FPoliSolutions LLC), F. Buschman, D. Aumiller (BAPL)
3365 On the Level of Approximation of the Multi-Dimensional Potential Flow Solution in Complex Geometries with Thermal-Hydraulic System Codes
C. Frepoli, J. P. Yurko, J. W. Fricano (FPoliSolutions LLC), F. Buschman, D. Aumiller (BAPL)
3378 Investigation of Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel with the System Code ATHLET
P. Pandazis, S. C. Ceuca, P. J. Schoeffel, H. V. Hristov (GRS)
3392 Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test
P. Papadolos, A. Sekhri (ETH Zurich), F. Giust (Axpo KN), P. Hidalga, R. Miró, T. Barrachina, G. Verdú (Univ Politècnica de València)
3406 The CATHARE Code Condensation Modelling Confronted to the TOPFLOW-PTS Steady-State Experiments
Pierre Gaillard, Dominique Bestion, Isabelle Dor, Philippe Germain, Frederic Moutin (CEA-DEN-DM2S-STMF)
Wednesday, September 2, 2015
8:00-9:00 am.
Wednesday Keynote Session—IV
3420 System Thermal Hydraulics for DBA Analysis and Simulation Status of Tools and Methods and Direction for Future R&D
D. Bestion (CEA)
Wednesday Keynote Session—V
3451 CFD Validation Experiments: What’s the Difference?
Barton L. Smith (Utah State Univ)
Wednesday Keynote Session—VI
3461 Severe Accident Research in Japan After Accident at Fukushima Daiichi NPS
Jun Sugimoto (Kyoto Univ)
Wednesday, September 2, 2015
9:00 a.m.-4:00 p.m.
Poster Session—I
Session Organizer: Elia Merzari (ANL)
3475 Six-Field Governing Equation Development for Advanced System Codes
Glenn Roth, Fatih Aydogan (Univ of Idaho)
3489 Experimental and Numerical Study of Valves for Supercritical Carbon Dioxide BRAYTON Cycle
Haomin Yuan, Mark Anderson (Univ of Wisconsin)
3503 Spatially-Resolved Measurement of Gas Phase Temperature and Velocity in the Subchannels of a Fuel Element during Dry-Out
Martin Arlit, C. Partmann (Technische Univ Dresden), E. Schleicher (Helmholtz-Zentrum Dresden-Rossendorf), U. Hampel (Technische Univ Dresden)
3511 Experimental and Analytic Study of the Damped Rocking Movement of a Cylindrical Shell in a Flowing Annular Channel
Benoit Migot, A. Malon (AREVA NP), R .J. Gibert (RJG-Conseil)
3525 An Experimental Study on the Quench Front Velocity and Temperature during Rewetting of a Hot Vertical Rod
Niki Lymperea, Andreas Nikoglou, Evangelos Hinis (National Technical Univ of Athens)
3539 On the Use of Hybrid RANS/LES Methods for the Simulation of the Erosion of a Stratified Layer by a Turbulent Buoyant Jet
Fabien Duval (IRSN), Michael Le Bars (IRPHE)
3550 Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant
Alejandro Carlos Mourgues, Thierry Muller, Florian Pedler, Arelia Lassauce, Michael Guillodo, Philippe Dolleans (AREVA NP), Marylise Charon-Charles (AREVA)
3565 A New Lumped Thermal Resistance Heat Transfer Model for Fuel Pin Structure
Shisheng Wang, Andrei Rineiski, Liancheng Guo (KIT)
3578 Assessment of the Best Estimate Thermal Design Method using THALES Subchannel Code
Byeong Il Jang (KEPCO Nuclear Fuel), Hong Ju Kim, Beomjun Jang, Shane Park, Chong Kuk Chun (KEPCO NF)
3589 Advanced Multiphysics Thermal-Hydraulics Models for the High Flux Isotope Reactor
Prashant K. Jain, James D. Freels (ORNL)
3604 Non-Linear Eddy Viscosity Turbulence Modeling in Hydra-TH for Fuel Related Applications
Benjamin Lawrence Magolan, Emilio Baglietto (MIT), Mark A. Christon (LANL), Thomas M. Smith (SNL)
3618 Diagnostic Techniques for Flow Induced Vibration
Shengjie Gong (Shanghai Jiao Tong Univ), Fujun Gan (Shanghai Nucl Eng Research Design Inst), Yong Mei, Chi Wang, Hanyang Gu (Shanghai Jiao Tong Univ)
3627 A Supercritical Pressure Parallel Channel Natural Circulation Loop
Manish Sharma, Kapil Bodkha, D. S. Pilkhwal, P. K. Vijayan (BARC)
3644 Quantification of Input Uncertainties Based on VEERA Reflooding Experiments
Torsti Ossian Alku (VTT Technical Research Centre of Finland Ltd)
3658 Implementation of Strong Implicit Procedure for the Energy Equations in Subchannel Code ATHAS
Wenjie Ding, Jianqiang Shan, Bo Zhang (Xi’an Jiaotong Univ)
3668 An Experimental Study on the Dynamics of a Liquid Film Under Shearing Force and Thermal Influence
Ke Wang, Youjia Zhang, Weimin Ma (Royal Inst of Technology)
3678 Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly
Seok-Kyu Chang, Dong-Jin Euh, Hae Seob Choi, Hyungmo Kim, Dong-Won Lee, Hyeong-Yeon Lee (KAERI)
3690 CTF Residual Formulation Solid Liquid Coupling
Christopher A. Dances, Maria Avramova (Penn State), Vince Mousseau (SNL)
3703 Visualization of Turbulent Thermal Mixing Structures in a Horizontal Stratified Condensing Flow
Seungtae Lee (KAERI)
3717 The Impact of Vertical Acceleration on the Nonlinear Behaviors of Multiple Parallel Boiling Channels
Jin-Der Lee, Chin Pan, Shaw-Wen Chen (National Tsing Hua Univ)
3731 Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code
Beomjun Jang, Chongkuk Chun, Joo Il Yoon, Byeong Il Jang (Kepco Nuclear Fuel), Dong Soo Song (KHNP)
3740 Uncertainty Analysis of an Interfacial Area Reconstruction Algorithm
Akshay Dave, Annalisa Manera (Univ of Michigan), Dirk Lucas, M. Beyer (Helmholtz-Zentrum Dresden-Rossendorf), M. Prasser (ETH Zurich)
3754 Experimental Investigation of Flat Plate Deflection Under Variable Velocity Parallel Flow
John C. Kennedy, Casey J. Jesse, Gerhard H. Schnieders, Gary L. Solbrekken (Univ of Missouri, Columbia)
3768 Uncertainty Quantification of TRACE Wall Heat Transfer Modeling in Subcooled Boiling Using BFBT Experiments
Guojun Hu, Tomasz Kozlowski, Caleb Brooks (Univ of Illinois)
3779 Steam Condensation in Packed Beds—An Experimental Study
Jacob Edwards, Daniel Gould (Kansas State Univ), Piyush Sabharwall (INL)
3793 Validation of the Dryout Modelling Code, FIDOM
Dinesh Kumar Chandraker, Arnab Dasgupta, A. K. Nayak, P. K. Vijayan (BARC), Kaushik Deshpande (Walchand College of Eng), S. P. Walker (Imperial College)
3802 A Reevaluation of the Lift Force in Eulerian Multiphase CFD
R. Segrue, E. Baglietto (MIT)
3817 Balance of Plant and Power Transmission for the Offshore Floating Nuclear Plant
Paolo Minelli, J. Buongiorno, M. Golay, N. Todreas (MIT)
Wednesday, September 2, 2015
9:30 a.m.-12:00 p.m.
Track 7: Advancements in Subchannel Analysis
Session Organizer: Elia Merzari (ANL)
3832 COBRA-IE: A New Sub-Channel Analysis Code
David L. Aumiller, G. W. Swartele, M. J. Meholic, L. J. Lloyd, F. X. Buschman (BAPL)
3846 Development of a Sub-Grid Liquid Jet Condensation Model
Francis X. Buschman, David L. Aumiller (BAPL)
3860 A Discussion of Uncertainty Quantification for CHF as Performed in COBRA-IE
David L. Aumiller, Michael J. Meholic (BAPL)
3874 An Assessment of Void Fraction Data with COBRA-IE
David L. Aumiller, Michael J. Meholic (BAPL)
3888 Large Open Region Interfacial Drag Modeling Package in COBRA-IE
David L. Aumiller (BAPL), Jeffrey W. Lane (Zachry)
3901 Assessment of Subchannel Code ASSERT-PV for Supercritical Applications
Yanfei Rao, Nihan Onder, Krishna Podila (Canadian Nuclear Laboratories Ltd.)
Track 7: The NURESAFE European Project: Multiscale Thermal Hydraulic Analysis—I
Session Organizer: Elia Merzari (ANL)
3915 CFD Simulation of the Departure from Nucleate Boiling
Ladislav Vyskocil, Jiri Macek (UJV Rez, a. s.)
3928 Implementation and Assessment of the Delayed Equilibrium Model for Computing Flashing Choked Flows into a Multi-Field CFD Code
Matthieu Duponcheel, Jean-Marie Alexandre Seynhaeve, Yann Bartosiewicz (Univ Catholique de Louvain)
3940 CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments
Vesa Tanskanen, Giteshkumar Patel, Markku Puustinen, Elina Hujala, Riitta Kyrki-Rajamäki, Juhani Hyvärinen (Lappeenranta Univ of Technology)
3954 Validation of CATHARE TH-SYS Code Against Experimental Reflood Tests
Sergii Lutsanych, Fabio Moretti, Francesco D’Auria (Univ of Pisa)
3968 Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel
In-Cheol Chu, Seung Jun Lee, Young Jung Youn, Jong Kuk Park, Hae Sup Choi, Dong Jin Euh, C.-H. Song (KAERI)
3979 Development and Assessment of a Method for Evaluating Uncertainty of Input Parameters
Andriy Kovtonyuk (Tractebel Eng), Sergii Lutsanych (Univ of Pisa), Alessandro Petruzzi (NINE), Fabio Moretti (Univ of Pisa)
Track 7: OECD/NEA Benchmark Study of the Accident at the Fukushima Dai-ichi Nuclear Power Plant—I
Session Organizer: Elia Merzari (ANL)
3993 An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents
Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Marco Pellegrini (Inst of Applied Energy), Masahiro Osakabe (Tokyo Univ of Marine Science and Technology), Andrea Achilli (SIET), Yukio Hanamoto (KAKEN)
4005 Fukusima Core Melt Composition Simulation with ASTEC
Herve Bonneville, L. Carenini, M. Barrachin (Inst de Radioprotection et de Sûreté Nucléaire)
4019 Lessons Learned from the Fukushima Analysis: The Modeling of Severe Accidents in Nuclear Power Plants
Luis E. Herranz, Claudia Lopez del Pra, Joan Fontanet, Elena Fernandez (CIEMAT)
4033 Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 Code
Toshinori Matsumoto, Jun Ishikawa, Yu Maruyama (JAEA)
4044 Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation
Haruyasu Nagai, Hiroaki Terada, Masamichi Chino, Genki Katata, Satoshi Mikami, Kimiaki Saito (JAEA)
4053 Benchmark Study of the Accident at the Fukushima Daiichi NPS: Best Estimate Case Comparison
Marco Pellegrini (The Inst of Applied Energy)
Track 1: Boiling and Condensation Fundamentals—I
Session Organizer: Caleb S. Brooks (Univ of Illinois)
4069 Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid
Giovanni Giustini, Janani Sree Murallidharan (Imperial College London), Yohei Sato, Bojan Niceno (Scherrer Inst), Vittorio Badalassi, Simon Walker (Imperial College London)
4083 Experimental Investigation of Heat Transfer Phenomenon of Annular Heat Pipe for Passive In-Core Cooling System
In Guk Kim, Kyung Mo Kim, Yeong Shin Jeong, In Cheol Bang (UNIST)
4097 Treatment of Nucleation and Bubble Dynamics in High Heat Flux Boiling
Yang Liu, Nam T. Dinh (NCSU)
4112 Modeling and Validation of Forced Convection Subcooled Boiling,
Dillon R. Shaver, Michael Z. Podowski (RPI)
4126 A Study of Heat Transfer Mechanisms and Flow Characteristics for Single Rising Taylor Bubbles
Jungho Kim, Alex Scammell (Univ of Maryland)
4139 Improvement of Wall Surface Temperature Evaluation Procedure During Subcooled Nucleate Boiling in Non-Empirical Boiling and Condensation Model
Yasuo Ose (Yamato System Engineer Co., Ltd.), Tomoaki Kunugi (Kyoto Univ)
Track 2: Computational Fluid Dynamics—III
Session Organizer: Si Young Lee (SRNL)
4153 Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation
Gemma Damiani, D. Rosa, Afaque Shams, E. M. J. Komen (NRG), E. Merzari, A. Obabko, P. Fischer (ANL)
4167 A Generalized Turbulent Dispersion Model for Bubbly Flow Numerical Simulation in NEPTUNE_CFD
Jerome Lavieville, Nicolas Merigoux, Mathieu Guingo, Cyril Baudry, Stephane Mimouni (EdF R&D)
4182 Numerical Study of Bubble Coalescence in Sub-Cooled Flow Boiling
Eyitayo Owoeye, DuWayne L. Schubring (Univ of Florida)
4196 CFD Evaluation of OECD PSBT Geometry Effects Based on Fluid Temperature Measurements
Yiban Xu, Yixing Sung, Emre Tatli (Westinghouse)
4208 CFD Modeling of Mixing Phenomena for Pressurized Thermal Shock Analysis on the DOWNCOMER of WWER-440
Maro Aghazarian, Tsolak Malakyan, Ashkhen Nalbandyan, Armen Amirjanyan (Nuclear and Radiation Safety Center)
4219 Implementation and Validation of a Surface Tension Model for the Multi-Scale Approach GENTOP
Gustavo A. Montoya, Emilio Baglietto (MIT), Dirk Lucas (Helmholtz-Zentrum Dresden-Rossendorf)
Track 6: Thermal Hydraulics in Sodium-Cooled Fast Reactors (Severe Accidents and Sodium-Water Reactions)—III
Session Organizer: Elia Merzari (ANL)
4233 Simulation of GR19 Sodium Boiling Experiments with CATHARE 2 System Code and TRIO_U MC Subchannel Code
Marine Anderhuber, Antoine Gerschenfeld, Nicolas Alpy, Jorge Perez, Jean-Marie Seiler (CEA)
4247 Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code
Stephane Mimouni, C. Baudry, M. Hassanaly, J. Lavieville, N. Mechitoua, N. Mérigoux (EdF R&D), V. Heisel (ENSEEIT)
4261 SLIMM Decay Heat Removal by Natural Circulation of Ambient Air
Luis Palomino, Mohamed S. El-Genk (Univ of New Mexico)
4275 Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor
Sunghyon Jang, T. Takata, A. Yamaguchi (Osaka Univ), A. Uchibori, A. Kurihara, H. Ohshima (JAEA)
4289 A Visual Study of Molten Metal Fuel Coolant Interactions Under an Initial Phase of SFR Severe Accident using Gallium Metal vs Water or R123
Hyo Heo, Seong Dae Park (Ulsan Natl Inst Sci Tech), Dong Wook Jerng (Chung-Ang Univ), In Cheol Bang (Ulsan Natl Inst Sci Tech)
4299 Single and Two-Phase Sodium Flow Analysis for two TUCOP CABRI Tests Using the ASTEC-Na Code
Sara Perez-Martin, Werner Pfrang (KIT), Giacomino Bandini, Stefano Ederli, Carlo Parisi (ENEA)
Track 1: Two-Phase Flow and Heat Transfer Fundamentals—IV
Session Organizer: Annalisa Manera (Univ of Michigan)
4313 Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow
Liang-ming Pan, Hui He, Yao Wu (Chongqing Univ), Peng Ju, Takashi Hibiki, Mamoru Ishii (Purdue Univ)
4323 Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions
Mengmeng Xi, Wenxi Tian, Siyang Huang, Guanghui Su, Suizheng Qiu (Xi’an Jiaotong Univ), Dongxiao Du (Shanghai Nucl Eng Research Design Inst)
4337 Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions
Jean-Marie Le Corre, Anders Hallehn, Henryk Tejne, Uffe Bergmann, Fredrik Waldemarsson (Westinghouse Electric Sweden AB), Boel Morenius (KTH), Ramine Baghai (RBI Instrumentation)
4352 Heat Loss Evaluation in Large Scale Rod Bundle CHF Experiments
Baowen Yang, Hui Zhang, Bo Zhang, (Xi’an Jiaotong Univ)
4366 Study on Flow Boiling Heat Transfer in Horizontal-Rectangular-Narrow-Flat Flow Channel
Yasuo Koizumi (JAEA), Koji Ohira (Japan Steel Works Ltd.)
Track 3: Experiments and Data Bases for Assessment and Validation (including of 3D Models)
Session Organizer: Xiaodong Sun (Ohio State)
4380 TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark
Haley Michelle Cowen, Scott Pfeffer, Juswald Vedovi, Lander Ibarra, David Vreeland, Dana Miranda (GE Hitachi Nuclear)
4394 Experimental Characterization of Interchannel Mixing Through a Narrow Gap
Simo A. Makiharju, Steven L. Ceccio (Univ of Michigan), John R. Buchanan, Alexander G. Mychkovsky, Kevin J. Hogan, Kirk T. Lowe (Bechtel Marine Propulsion Corp.)
4410 Assessment of Multi-Dimensional Component of Mars with Air-Water Cross Flow Experiment
Jin-Hwa Yang, Chi-Jin Choi, Hyoung-Kyu Cho, Goon-Cherl Park (Seoul Natl Univ), Dong-Jin Euh (KAERI)
4424 Validation of CATHARE 3 Code on the PIERO Experiment
Roberto Freitas (IRSN), Yann Di Pasquale (CS-SI)
4436 Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows
Benedikt Krohn, Medhat Sharabi (Paul Scherrer Inst), Bojan Niceno, Horst-Michael Prasser (Paul Scherrer Inst/ ETH Zürich), Henny Bijleveld, Afaque Shams, Ferry Roelofs (NRG)
4450 A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000
M. Duan, Y. Chen, Y. Lv, W. Li, K. Bi, W. Wang, K. Du (China Inst of Atomic Energy)
Track 5: Hydrogen and Fission Product Behavior
Session Organizer: Elia Merzari (ANL)
4462 Erosion of a Confined Stratified Layer by a Vertical Jet-Detailed Assessment of a CFD Approach Against the OECD/NEA PSI Benchmark
Stephan Kelm (FjZ), Ralf Kapulla (Paul Scherrer Inst), Hans-Josef Allelein (RWTH Aachen Univ)
4476 Development and Qualification of an Aerosol Generator for Investigations Under Thermal-Hydraulic Severe Accident Boundary Conditions
Bjoern Alexander Krupa (Inst for Reactor Safety and Reactor Technology), Paul-Martin Steffen (Safety Research and Reactor Technology), Jeffrey Kobalz, Hans-Josef Allelein (Inst for Reactor Safety and Reactor Technology)
4490 Parametric Study on Density Stratification Erosion Caused by a Horizontal Steam Jet Interacting with a Vertical Plate Obstruction
Sidharth Paranjape, Ralf Kapulla, Guillaume Mignot, Domenico Paladino (Paul Scherrer Inst)
4504 Calculation of the Probability of DDT during Severe Accidents
Wison Luangdilok, E. van Heerden, P. McMinn (Fauske & Assoc, LLC)
4516 Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer
Jianjun Xiao (KIT), John R. Travis (Eng and Scientific Software Inc.), Reinhard Redlinger, Mike Kuznetsov, Anatoly Svishchev, Wolfgang Breitung, Thomas Jordan (KIT)
Track 3: Plant System Code Validation—III
Session Organizer: Xiaodong Sun (Ohio State)
4529 Evaluation of RELAP5/MOD3.2 for ACP1000 Passive Residual Heat Removal System
Houjun Gong, Zhao Xi, Yanping Huang (Nuclear Power Inst of China)
4540 Simulation of Esprit of Hualong Secondary Passive Residual Heat Removal System by Using RELAP5
Feng Li (Science and Technology on Reactor System Design Technology Laboratory)
4548 Validation of RELAP5/MOD3.3 Against a Load Step Transient at RINGHALS 4 NPP
Jozsef Banati (Chalmers Univ of Technology), Magnus Holmgren (Ringhals AB)
4562 Development of TALL-3D Test Matrix for APROS Code Validation
Ignas Mickus, Kaspar Kööp, Marti Jeltsov, Dmitry Grishchenko, Pavel Kudinov (KTH), Jari Lappalainen (VTT Technical Research Centre of Finland)
4576 Validation of MARS-LMR Code for Heat Transfer Models in the DHRS of the PGSFR
Chiwoong Choi, Kwiseok Ha (KAERI)
4590 Reactor Core Isolation Cooling TRACG Model
Sam Lafountain (GE Hitachi), Charles Heck (Global Nuclear Fuels), Necdet Kurul (GE Hitachi)
Wednesday, September 2, 2015
1:30-3:35 p.m
Track 7: Corium Research Platform: Past and Future—I
Session Organizer: Elia Merzari (ANL)
4604 Severe Accident Facilities for European Safety Targets,
Alexei Miassoedov (KIT) Christophe Journeau (CEA), Sevostian Bechta (KTH), Zoltan Hozer (MTA EK), Dario Manara, David Bottomley (EC-JRC-ITU), Monika Kiselova (UJV), Gert Langrock (AREVA)
4617 Needs for Large Mass Phototype Corium Experiments: The PLINIUS-2 Platform
Christophe Journeau, Laurence Buffe, Jean Fram;ois Haquet, Pascal Pi/uso, Guy Willermoz (CEA)
4631 Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core-Concrete Interaction
Kevin R. Robb, Matthew W. Francis (ORNL), Mitchell T. Farmer (ANL)
4646 Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability
Mitchell T. Farmer, Steve Lomperski, Craig Gerardi, Nathan Bremer (ANL), Sud Basu (NRC)
4661 Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis
Mike Corradini (Univ of Wisconsin, Madison), Phillip Ellison (GE Power and Water), Mitchell T. Farmer (ANL), Matthew Francis (ORNL), Jeff Gabor (Erin Engineering), Randy Gauntt (SNL), Roy Linthicum (Exelon Corp.), Chan Paik, Martin Plys (Fauske and Associates LLC), Cristian Rabiti (INL), Joy Rempe (Rempe and Assoc LLC), Kevin Robb (ORNL), Richard Wachowiak (EPRI)
Track 7: Thermal Hydraulic Experiments and Numerical Analysis in Support of MYRRHA—III
Session Organizer: Elia Merzari (ANL)
4675 Transient Analyses for the MYRRHA-FASTEF Reactor by SIMMER Code
Morena Angelucci, M. Eboli, N. Forgione (Univ of Pisa), G. Bandini (ENEA)
4689 CFD and Experimental Investigation of Sloshing Parameters for the Safety Assessment of HLM Reactors
Konstantinos Myrillas, Philippe Planquart, Jean-Marie Buchlin (von Karman Inst), Marc Schyns (SCK/CEN)
4703 Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor
Francesco Andreoli (Univ of Pisa), Dario Bisogni, Francesco Belloni, Guy Scheveneels, Katrien Van Tichelen (SCK/CEN)
4717 Numerical Analysis of MYRRHA Control Rod System Dynamics
Graham Kennedy (SCK/CEN), Maria Manuela Profir, Vincent Moreau (CRS4)
4731 Safety Analysis of the MYRRHA Reactor
Diego Castelliti, Katrien Van Tichelen, Gert Van den Eynde, Baudouin Arien (SCK/CEN)
Track 4: Instabilities and Nonlinear Dynamics
Session Organizer: Elia Merzari (ANL)
4745 A Method to Prevent Severe Power and Flow Oscillations in Boiling Water Reactors
Yousef M. Farawila (Farawila et al., Inc.)
4757 TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark
Abdelhamid Dokhane, Omar Zerkak, Hakim Ferroukhi (Paul Scherrer Inst), Ivan Gajev (Bulgarian Nuclear Regulatory Agency), Jerry Judd (Studsvik Scandpower, Inc.), Tomasz Kozlowski (Univ of Illinois)
4771 Simulation of the Inadvertent Rod Cluster Control Assembly Bank Withdrawal at Power for ANGRA I NPP using an LQR Digital Controller
M. A. Bayout Alvarenga (National Commission of Nuclear Energy), J. A. C. Canedo Medeiros, J. J. Rivero Oliva, Paulo Fernando F. Frutuoso e Melo (COPPE, Federal University of Rio de Janeiro)
4784 A Physical Mechanism for Rotating Lines of Symmetry in BWR Out-of-Phase Limit Cycle Oscillations
Aaron Wysocki, Annalisa Manera, Thomas Downar (Univ of Michigan), Jose March-Leuba (ORNL)
Track 1: Boiling and Condensation Fundamentals—II
Session Organizer: Caleb S. Brooks (Univ of Illinois)
4798 Influence of Boiling Initiation Surface Superheat on Subcooled Water Flow Boiling Critical Heat Flux in a SUS304 Circular Tube at High Liquid Reynolds Number
Koichi Hata (Kyoto Univ), K. Fukuda (Kobe Univ.), S. Masuzaki (NIFS)
4812 Subcooled Boiling-Induced Vibration of a Single Heater Rod Confined with Metallic Walls
Kenji Takano, Yusuke Hashimoto, Tomoaki Kunugi, Takehiko Yokomine, Zensaku Kawara (Kyoto Univ)
4826 Roles of Boiling Surface Characterized by Micro-Structures on Boiling Heat Transfer and Critical Heat Flux
Seol Ha Kim, Jun Young Kang, Hyun Sun Park, Moriyama Kiyofumi, Moo Hwan Kim (POSTECH)
4838 Observation of CHF Phenomena Based on a Visualization of Near Wall Boiling Structure in Vertical Narrow Channel Submerged in a Pool
In-Cheol Chu, Dong Jin Euh, Chul-Hwa Song (KAERI)
4848 Microlayer Models for Nucleate Boiling Simulations: The Significance of Conjugate Heat Transfer
Susann Haensch (Imperial College London), Chidu Narayanan, Sylvain Reboux (ASCOMP GmbH), Giovanni Giustini, Simon Peter Walker (Imperial College London)
Track 2: Accuracy and Uncertainty Analysis
Session Organizer: Annalisa Manera (Univ of Michigan)
4862 A Methodology for Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model using TRACE
Damar Canggih Wicaksono (Ecole Polytechnique Fédérale de Lausanne), Omar Zerkak (Paul Scherrer Inst), Andreas Pautz (Ecole Polytechnique Fédérale de Lausanne)
4880 Nodalization Schemes for Lumped-Parameter Calculations of Representative Nuclear Reactor Severe Accident Tests in the MISTRA Facilty
Sonia Benteboula, Frederic Dabbene (CEA)
4894 Uncertainty and Sensitivity Analysis of COBRA-TF for the OECD LWR UAM Benchmark using DAKOTA
Nathan W. Porter, Maria N. Avramova, Kostadin N. Ivanov (Penn State)
4907 Use of Deterministic Sampling for Uncertainty Quantification in CFD
Peter Karl Martin Hedberg (SSM), Peter Jan Hessling (SP Technical Research Inst of Sweden)
4921 Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Pool
Fulvio Mascari, Felice De Rosa (ENEA), Hideo Nakamura (JAEA/Nuclear Safety Research Center), Klaus Umminger (AREVA), Francesco D’Auria (Univ of Pisa / San Piero a Grado Nuclear Research Group
Track 6: Thermal Hydraulics of Advanced Reactors: General
Session Organizer: Elia Merzari (ANL)
4935 Conceptual Design of Tritium Removal Facility for FHRs
Xiao Wu, David J. Arcilesi., Xiaodong Sun, Richard Christensen (Ohio State Univ), Piyush Sabharwall (INL)
4949 Study on Startup Characteristics of Heat Pipe Cooled Space Reactor
Yuan Yuan, Jianqiang Shan, Bin Zhang, Junli Gou, Bo Zhang (Xi’an Jiaotong Univ)
4961 Accident Analysis of Heat Pipe Cooled Space Reactor
Yuan Yuan, Jianqiang Shan, Bin Zhang, Junli Gou, Bo Zhang (Xi’an Jiaotong Univ)
4972 Characterization of Tritium Transport in the FLibe-Graphite System, for In-Situ Tritium Absorption by the Fuel Elements of the Fluoride-Salt-Cooled High-Temperature Reactor (FHR)
Michael Charles Young, Huali Wu, Raluca O. Scarlat (Univ of Wisconsin, Madison)
4987 Preliminary Analysis of the Afterheat Removal in Pebble Bed Fluoride Salt Cooled High Temperature Reactors Under Accident Conditions
Qiming Li, Shende Sun, Wen Zhou, Naxiu Wang (Chinese Academy of Sciences)
Track 1: Natural Circulation, Passive Safety Systems and Related Phenomena —I
Session Organizer: Paolo Ferroni (Westinghouse)
4994 Passive Decay Heat Removal System Design for the Integral Inherent Safety Light Water Reactor (I2 S-LWR)
Mingjun Wang (Xi’an Jiaotong Univ/Univ of Michigan), Annalisa Manera (Univ of Michigan), Matthew J. Memmott (Brigham Young Univ), Suizheng Qiu (Xi’an Jiaotong Univ)
5008 Experimental Study of Laminar Mixed Convection in a Rod Bundle with Mixing Vane Spacer Grids
Lokanath Mohanta, Fan-Bill Cheung (Penn State), Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie (NRC)
5020 Heat Transfer Analysis of Horizontal U-Shaped Heat Exchanger Submerged in a Pool using MARS Code
Seongsu Jeon, Soon-Joon Hong (Inst of Future Energy Technology), Hyoung-Kyu Cho, Goon-Cherl Park (Seoul Natl Univ)
5034 Numerical Simulation of Air Natural Circulation and Thermal Radiation in Passive Containment System
Weizhong Zhang, Qian Lin (Shanghai Nucl Research Design Inst)
5044 Analysis of Reverse Flow in Low-Rise Inverted U-Tube Steam Generator of PWR Factel Facility
O-P Kauppinen, V. Riikonen, V. Kouhia, J. Hyvarinen (Lappeenranta Univ of Technology)
Track 5: Modeling and Experiments of Severe Accidents—III
Session Organizer: Elia Merzari (ANL)
5058 Analytical Modelling of the Primary Phase of an Unprotected Loss of Flow
Jean-Baptiste Droin, Nathalie Marie, Frederic Bertrand (CEA), Elsa Merle-Lucotte (CNRS-IN2P3)
5072 COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers
Luteng Zhang, Yukun Zhou, Yapei Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (Xi’an Jiaotong Univ)
5084 Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique
Faruk Ahmed Sohag, F. R. Beck, L. Mohanta, F. B. Cheung, A. E. Segall, T. J. Eden, J. Potter (Penn State)
5098 Modeling of Ex-Vessel Melt Pool Coolability Under Bottom Flooding with Decay Heat Simulation
Nitendra Singh (Homi Bhabha National Inst), Parimal P. Kulkarni, Arun K. Nayak (BARC)
5112 MAAP BWR and PWR Lower Plenum Model Improvements
Sung Jin Lee, Basar Ozar, Chan Y. Paik, Quan Zhou, Paul McMinn, Michael Epstein (Fauske & Associates, LLC)
Track 4: Operation and Safety of Existing Reactors: General—I
Session Organizer: Xiaodong Sun (Ohio State)
5126 On the Aspect of Evaluation of Critical Channel Power and Associated Uncertainty in CANDU Slow Loss of Regulation Event Analysis
Yujun Guo, N. Hammouda (Canadian Nucl Safety Comm)
5137 Experimental Test Facility Data Synthesis with the Dynamical System Scaling Methodology
Cesare Frepoli, Joseph P. Yurko (FPoliSolutions LLC), Jose N. Reyes (NuScale Power LLC)
5152 Demonstration of Test Facility Design Optimization with the Dynamical System Scaling Methodology
Cesare Frepoli, Joseph P. Yurko (FPoliSolutions LLC), Jose N. Reyes (NuScale Power LLC)
5169 A Top-Down Scaling Analysis for the ROSA-IV/LSTF Integral Effects Test Facility to Support Applying the WCOBRA/TRAC-TF2 System Code to a Three-Loop Small Break LOCA
Jun Liao, Katsuhiro Ohkawa (Westinghouse STD)
5183 LBLOCA Uncertainty Analysis using META Models
Jose Felipe Villanueva, Francisco Sánchez-Sáez, Ana Isabel Sánchez, Sebastián Martorell (Univ Politècnica de Valéncia)
Track 4: NPP Transient and Accident Analysis—III
Session Organizer: Elia Merzari (ANL)
5194 Sources and Effects of Non-Condensable Gases in Reactor Coolant System of LWR
Pavel Kral (UJV Rez, a. s.), Juhani Hyvarinen (Lappeenranta Technical Univ), Andrej Prosek (Jožef Stefan Inst), Attila Guba (MTA Centre for Energy Research)
5209 Analysis of the AP1000® Passive Containment Cooling System Air Flow Path Using Computational Fluid Dynamics
Richard F. Wright, Xu Hong, Megan Durse (Westinghouse STD), Todd Sutton (Westinghouse)
5222 Application of CFD Towards the Thermo-Hydraulic Analysis of Spent Fuel Pool Accidents
Ronald Oertel, Eckhard Krepper, Dirk Lucas (Helmholtz-Zentrum Dresden-Rossendorf)
5236 Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool
Li Ge, Junli Gou, Jianqiang Shan, Bin Zhang, Bo Zhang, Zijiang Yang (Xi’an Jiaotong Univ)
5250 Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR
Che-Hao Chen, Kai-Chun Huang, Shao-Wen Chen (Natl Tsing Hua Univ), Jong-Rong Wang, Chunkuan Shih (Nuclear and New Energy Education and Research Foundation), Show-Chyuan Chiang, Chia-Chuan Liu (Taiwan Power Co.), Hao-Tzu Lin (INER)
Wednesday, September 2, 2015
4:00-6:05 p.m.
Track 7: Addressing the GSI-191: Progress in Methodologies and Technologies—I
Session Organizer: Elia Merzari (ANL)
5263 Experimental Observations of Boric Acid Precipitation Scenarios
Rodolfo Vaghetto, Saya Lee, Yassin A. Hassan, Ernie John Lowry Kee (Texas A&M)
5275 Overview of the Flume Integral Effects and Separate Effects Testing and Analysis (FIESTA) Facility for Investigating Containment Debris Transport and Sump Strainer Head Loss
Cody Williams, Daniel P. LaBrier, Edward D. Blandford (Univ of New Mexico)
5289 Investigation of the Release of Zinc in the Reactor Sump and the Behavior of Dissolved Zinc at Hotspots in the Reactor Core after a Loss of Coolant Accident
Stefan Renger, Soeren Alt, Wolfgang Kaestner, Andre Seeliger (Univ of Applied Sciences Zittau/Görlitz), Holger Kryk (Helmholtz-Zentrum Dresden-Rossendorf)
5303 Conventional and Chemical Head Loss Modeling of Multi-Constituent Debris Beds in Resolution of GSI-191
Amir F. Ali, Edward D. Blandford (Univ of New Mexico)
5317 The Effect of Electric Potential on Fibrous Debris Bypass Through a Containment Sump Strainer
Saya Lee, Rodolfo Vaghetto, Jean Lim, Matthew J. Kappes, Yassin A. Hassan (Texas A&M)
Track 7: Important Severe Accident Research Issues after Fukushima Accidents
Session Organizer: Jun Sugimoto, P.E. (Kyoto Univ)
5327 Plinius Prototypic Corium Experimental Platform: Major Results and Future Works
Viviane Bouyer, Nathalie Cassiaut-Louis, Pascal Fouquart, Pascal Piluso (CEA, DEN, Cadarache, SMTA/LPMA)
5341 Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident
Taisuke Yonomoto, Yasuteru Sibamoto, Takeshi Takeda, Akira Sato, Masahiro Ishigaki, Satoshi Abe, Yuria Okagaki, HaoMin Sun, Daisuke Tochio (JAEA)
5353 New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident
Hideo Nakamura (JAEA /Nuclear Safety Research Center), Kenji Arai, Hirohide Oikawa (Toshiba), Tadashi Fujii (Hitachi-GE Nuclear Engineering), Shigemitsu Umezawa (Mitsubishi Heavy Industry), Yutaka Abe (Univ of Tsukuba), Jun Sugimoto (Kyoto Univ), Seiichi Koshizuka, Akira Yamaguchi (Univ of Tokyo)
5367 Molten Core Relocation Analysis of CORA-17 and CORA-18 for SAMPSON/MCRA Validation
Andrea Prestigiacomo (Politecnico di Milano), Marco Pellegrini, Alessandro Costa, Masanori Naitoh (The Inst of Applied Energy), Hisashi Ninokata (Politecnico di Milano)
Track 7: Advancements in SFR Thermal Hydraulics
Session Organizer: Elia Merzari (ANL)
5380 Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient
Ivan Horvatovic, Chirayu Batra, Marco Cherubini, Alessandro Petruzzi, Francesco D’Auria (Gruppo di Ricerca Nucleare San Piero a Grado), Tomislav Bajs (Enconet d.o.o.)
5391 Pseudo 3-D Full-Core Conjugate Heat Transfer Modeling of Sodium Fast Reactors
Rui Hu, Yiqi Yu (ANL)
5405 Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation
Sujin Yeom, Jonggan Hong, Jae-Hyuk Eoh, Jong-Man Kim, Youngil Cho, Min-Hwan Jung, Da-Young Gam, Tae-Joon Kim, Inkoo Hwang, Jewhan Lee, Ji-Young Jeong, Chungho Cho (KAERI)
5416 Structure-Based Resolution of Turbulence for Sodium Fast Reactor Thermal Striping Applications
Michael Acton, Giancarlo Lenci, Emilio Baglietto (MIT)
5430 Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire-Wrap Spacer
Seong Dae Park, Sung Bo Moon, Seok Bin Seo, In Cheol Bang (UNIST), R. Robb (ORNL)
Track 5: Natural Convection and Mixing Phenomena, Modeling and Experiments
Session Organizer:. Elia Merzari (ANL)
5445 Natural Convection Heat Transfer Characteristics of KUR Fuel Assembly during Loss of Coolant Accident
Daisuke Ito, Yasushi Saito (Kyoto Univ)
5456 Performance of Hydrogen Mitigation Systems for a Scaled Accident Scenario: Overview of Ercosam Project Experimental Results for the Panda Facility
Guillaume Mignot, Ralf Kapulla, Sidharth Paranjape, Domenico Paladino (Paul Scherrer Inst)
5470 Benchmark of LIVE Experiments with MAAP5.04 Alpha
Basar Ozar, Sung J. Lee, Michael Epstein, Chan Y. Paik (Fauske & Assoc LLC)
5484 Investigation of MCCI Phenomena with Multi-Physics MPS Simulation
Penghui Chai, Nedjet Erkan, Masahiro Kondo, Koji Okamoto (Univ of Tokyo)
Track 6: Thermal Hydraulics in Small Modular Reactors—II
Session Organizer: W. David Pointer, Ph.D. (ORNL)
5498 Experimental Stability Maps for a BWR-Type Small Modular Reactor
Shanbin Shi, Yuchen Lin, Won Sik Yang, Mamoru Ishii (Purdue Univ)
5512 Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor
Adam Brigantic, Wade R. Marcum (Oregon State Univ)
5526 NRELAP5 Predictions of KAIST High Pressure Condensation Data Using Existing and Extended Shah Condensation Correlation
Pravin Sawant, John Marking, Claudio Delfino (NuScale Power LLC)
5536 Comparison of COBRA-TF and VIPRE-01 Against Low Flow Code Assessment Problems
Azat Galimov, Claudio Delfino (NuScale Power LLC), Michael Bradbury (Information Systems Laboratories, Inc.), Garry Gose (Zachry Nuclear Eng, Inc), Robert Keith Salko (ORNL)
5546 Analytical Stability Analogue for a Single-Phase Natural Circulation Loop
Yousef M. Farawila, Donald R. Todd (Farawila et al., Inc.), Maurice J. Ades (NuScale Power, LLC)
Track 1: Two-Phase Flow and Heat Transfer Fundamentals—V
Session Organizer: Seungjin Kim (Penn State)
5559 Characterization of Horizontal Air-Water Two-Phase Flow
Ran Kong, Seungjin Kim (Penn State)
5573 Effects of Steam-Water vs. Air-Water Fluid Pairs and Pressure on Flooding in Large Diameter Tubes
Karen Vierow, Nicholas Mohammed (Texas A&M), David Aumiller (BAPL)
5587 Inlet Effects on Vertical-Downward Air-Water Two-Phase Flow
Shouxu Qiao, Daniel Mena, Seungjin Kim (Penn State)
5601 Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend
Ki-Won Song, Nguyen T. Hung, Hyun Sun Park, Shripad T. Revankar (POSTECH), Bo W. Rhee, Kwang Soon Ha, Rae-Joon Park, Jin Ho Song (KAERI)
5614 Onset of Flow Instability Due to the Mergence of Facing Bubble Layers in a Vertical Narrow Rectangular Channel
Juhyung Lee, Soon Heung Chang, Yong Hoon Jeong (KAIST)
Track 5: Modeling and Experiments of Severe Accidents—IV
Session Organizer: Elia Merzari (ANL)
5627 CHF Experiment of RPV Lower Head with Real Surface Material for ERVC-IVR Strategy
Wei Lu, Ming Zhang, Teng Hu, Huajian Chang (State Nuclear Power Research Inst)
5637 Turbulent Convection Experiment to Support IVR Strategy
Ma Li, Jing Li, Shui Ji, Huajian Chang (State Nuclear Power Technology Research & Development Centre)
5648 Model Development of UO2-ZR Plate Fuel Behavior at Early Phase of Severe Accident and Molten Fuel Meat Relocation
Zhang Zhuohua, Peng Shinian (Nuclear Power Inst of China)
5658 Live Experiments on the In-Vessel Melt Pool Behaviour with Different External Cooling Conditions and the Simulation Results with a Coupled MELCOR-PECM Approach
Philipp Dietrich, Xiaoyang Gaus-Liu, Alexei Miassoedov, Frank Kretzschmar, Andreas Class (KIT)
5672 Heat Up and Potential Failure of BWR Upper Internals during a Severe Accident
Kevin Banfield (GE Hitachi Nuclear)
Track 4: Operation and Safety of Existing Reactors: General—II
Session Organizer: Elia Merzari (ANL)
5687 Safety Margins after Failure of Fuel Cladding during Protected Loss-of-Heat-Sink Accidents in a Sodium-Cooled Fast Reactor
Yoshitaka Fukano (JAEA), Masahiro Nishimura, Fumiaki Yamada, Takero Mori (JAEA)
5699 Uncertainty Analysis for Lift-Forces on BWR Fuel Assemblies
Carl Adamsson (Vattenfall Nuclear Fuel), Carolin Holmkvist (Uppsala Univ)
5709 Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction
Gunyeop Park, Soo Jae Kim, Hyun Soo Kim, Sun Ryung Oh, Hyun Sun Park, Moo Hwan Kim, Je Hyun Baek (POSTECH)
5720 Comparison of Some Approaches for the Estimation of Tolerance Limits in the Context of LBLOCA Uncertainty Analysis
Jose Felipe Villanueva, Francisco Sánchez-Sáez, Ana Isabel Sánchez, Sebastián Martorell (Univ Politècnica de Valéncia)
Track 4: NPP Transient and Accident Analysis—IV
Session Organizer: Elia Merzari (ANL)
5734 Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study based on a Station Blackout Scenario
Saidur Rahman, D. R. Karanki, A. Epiney, O. Zerkak, V. N. Dang (Paul Scherrer Inst)
5748 Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents
Tadashi Watanabe (Univ of Fukui)
5756 A Dynamic Model of Hydrostatic Reactor Coolant Pump Seals for RELAP5/MOD3.3
Michael Anthony LaPresti, Naugab E. Lee, Ruben Espinosa, Michael Volodzko, Mie Azuma (Westinghouse)
5770 Core Exit Thermocouple Response to Inadequate Core Cooling Using CFD Dynamic Mesh
Liping Cao, Josh Hartz, Hong Xu, Justin Figley (Westinghouse)
5784 TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology
Dana C. Miranda, D. G. Vreeland, C. McElroy, J. Yang, J. Vedovi, J.
Thursday, September 3, 2015
8:00-9:00 a.m.
Thursday, Keynote Session—VII
5798 Issues and Challenges on Advanced Thermal-Hydraulic Safety Research
Chul-Hwa Song (KAERI)
Thursday, Keynote Session—VIII
5816 DNS Assisted Modeling of Bubbly Flows in Vertical Channels
G. Tryggvason, M. Ma, J. Lu (Univ of Notre Dame)
Thursday, Keynote Session—IX
5829 A Regulator’s Perspective on the State-of-the-Art in Nuclear Thermal-Hydraulics
Stephen M. Bajorek (NRC)
Thursday, September 3, 2015
9:00 a.m.-4:00 p.m.
Poster Session—II
Session Organizer: Xiaodong Sun (Ohio State)
5840 Numerical Simulations of Turbulent Mixing Factor in 2x2 Rod Bundles at Supercritical Pressures
Jinguang Zang, Xiao Yan, Daiquan Du, Xiaokang Zeng, Yanping Huang (Nuclear Power Inst of China)
5861 Plateau Facility in Support to ASTRID and the SFR Program: An Overview of the First Mock-Up of the ASTRID Upper Plenum MICAS
D. Guénadou, I. Tkatschenko, P. Aubert (CEA)
5873 Design of a Unit Cell Facility for Studies of the Prismatic VHTR Lower Plenum
D. Tyler Landfried, Paul Kristo, Mark Kimber (Univ of Pittsburgh)
5886 GOTHIC 8.1 Benchmark to THAI Facility Experiment with Steam-Helium Stratification
T. Moore, T. L. George (Numerical Applications)
5900 Hot Channel Analysis of a 333 MWth Civil Nuclear Marine Core using the COBRA-EN Code
Syed Bahauddin Alam, Benjamin A. Lindley, Geoffrey T. Parks (Univ of Cambridge)
5914 CTF Application to BWR Modeling and Simulations
C. Gosdin, M. Avramova (Penn State), R. Salko (ORNL)
5928 Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor
K. H. Kang, Y. S. Park, J. R. Kim, B. U. Bae, N. H. Choi, K. Y. Choi (KAERI)
5937 Loss of Coolant Flow Accident Analysis for Fluoride Salt Cooled High Temperature Reactor
Yao Fu, Yang Yang, Yang Zou, Qaing Sun, Jie Zhang (Chinese Academy of Sciences)
5948 Comparison and Analysis on Integral Small Modular Reactor with Two Different ESF Designs Response to Postulated Events
Guoxu Zhang, Heng Xie (Tsinghu Univ)
5962 Instrumentation for Temperature and Heat Flux Measurement on a Solid Surface under BWR Operating Conditions
M. Bergagio, S. Hedberg, S. Rydström, Henryk Anglart (KTH)
5976 Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support
Xiong Yiqiang, Jing Liu, Haidan Wang, Gang Chen, Wei Bai, Huie Sha, Yixue Chen (SNPTC)
5986 SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments
Y. Y. Vinogradova, M. E. Kuznetsova, N. I. Ryzhov, V. N. Semenov, E. V. Usov, R. V. Chalyy (RAS)
5996 Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using Core SCDAP Components
J. Freixa, M. Perez-Ferragut, F. Reventos (UPC), C. M. Allison, J. K. Hohorst (ISS)
6008 Comparison Analysis of CHF Parametric Trends in Vertical Tube and 5x5 Bundle
Shumiao Wang, Jianqiang Shan, Bo Zhang (Xi’an Jiaotong Univ), Xuemei Lang (NPIC)
6020 Effects of Additives on CHF Behaviors for ERVC-IVR Strategy with FIRM Facility
Yang Sheng, Lu Wei, Hu Teng, Chang Huajian, (State Nuclear Power Research Inst)
6030 RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal
M. Perez, J. Freixa, , E. Mas de les Valls (Technical Univ of Catalonia), T. Sandeep, V. Chaudhari (Inst for Plasma Research)
6044 Graphite Oxidation Rates in Comparison to Regimes with Application to the Oregon State Over University High Temperature Test Facility
Jorday Coy, Brian Woods, Matt Hertel Evan Peters (Oregon State Univ)
6055 MARS Code Evaluation of Reflood Phenomena in a Partially-Deformed 5x5 Rod Bundle
B. J. Kim, J. Kim, K. Kim, S. K. Moon, C.-H. Song (KAERI)
6064 CTF Void Drift Validation
M. Gergar, M. Avramova (Penn State), R. Salko (ORNL)
6076 Developments on High Pressure Two Phase Flow Measurement Techniques
H. Schmidt, L. Dennhardt, D. Hille, I. Ganzmann, O. Herbst, L. Klemm, M. Rehm, K. Umminger, E. Peter, D. Gordon (AREVA GmbH)
6088 Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor
Hyungmo Kim, Dong-Won Lee, Yung Joo Ko, Seok-Kyu Chang, Sun Rock Choi, Hae Seob Choi, Hyeon Seok Woo, Dong-Jin Euh, Ji-Young Jeong, Hyeong-Yeon Lee (KAERI)
6096 Experimental Study of Condensation Heat Transfer in the Presence of Noncondensable Gas on the Vertical Tube
Yeong-Jun Jang, Dong-Jae Choi, Yeon-Gun Lee (Jeju National Univ), Sin Kim, Dong-Wook Jerng (Chung-Ang Univ)
6110 A Simple and Efficient Steam Generator Design for Integral SMRs
M. Ilyas, M, A. Khan (Pakistan Inst of Eng and Applied Sciences)
6116 Study on the Improvement of TOPAZ-II System by using a Heat Pipe Radiator
Wenwen Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (Xi’an Jiaotong Univ)
6130 Preliminary Steady State and Transient Analysis of a Molten Salt Based Reactor using RELAP/SCDAPSIM/MOD4.0
Shuying Jiang, Maosong Cheng, Zhimin Dai, Guimin Liu (Chinese Academy of Sciences)
6141 Verification and Validation of a Fuel-Rod Temperature Analysis Code-BIRCH
J. L. Ruan, Y. B. Zhu, J. G. Li (China Nuclear Power Technology Research Inst)
6155 A Specialized Thermal-Hydraulic Code with Porous Media Model and SIMPLEC Algorithm for PB-FHRs
Yanzhi E, Yang Zou, Hongjie Xu, Shixiong Song, Jie Zhang (Chinese Academy of Sciences)
6169 Experimental and Modeling Studies of Over-Cooling Transients in Fluoride-Salt Cooled High-Temperature Reactors
F. Carotti, M. Abou Dbai, K. Ahmed, R. O. Scarlat (Univ of Wisconsin, Madison)
6183 Analysis on UCRW-ATWS in TMSR-SF1
Bo Xu, Yang Zou, Xiaohan Yu, Yao Fu, Qiang Sun, (Chinese Academy of Sciences)
6195 An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation
Hwang Bae, Sung Uk Ryu, Sung-Jae Yi, Hyun-Sik Park (KAERI), Yeon-Sik Cho, Jae-Seung Suh (System Eng and Technology)
6208 Development of a Computational Model to Determine Performance of a Self-Priming Venturi Scrubber for Thorium Reactor
Paridhi Goel (Homi Bhabha National Inst), Avinash Moharana (BARC), A. K. Nayak (Homi Bhabha National Inst/BARC)
6217 Effect of a Blockage Length on the Coolability during Reflood in a 2x2 Rod Bundle with a 90% Partially Blocked Region
Kihwan Kim, Byung-Jae Kim, Hae-Seob Choi, Sang-Ki Moon, Chul-Hwa Song (KAERI)
6229 Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution
M. G. Mankosa, C. J. Piotrowski, M. N. Avramova, A. T. Motta, K. N. Ivanov (Penn State), S. Stafford, R. L. Williamson (INL)
September 3, 2015
9:30 a.m.-12:00 p.m.
Track 7: Critical Heat Flux in Fuel Bundle: Modeling, Prediction, and Experimental Measurements—I
Session Organizer: Elia Merzari (ANL)
6243 Margins to Critical Heat Flux in Pressurized Water Reactors using Modern Thermal-Hydraulic Methods
Christophe Herer (IRSN)
6257 Comparison of Experimental Critical Heat Flux Data to Prediction Methods for Conditions Prototypical of Light Water Small Modular Reactors
M. S. Greenwood, J. P. Duarte, M. Corradini (Univ of Wisconsin, Madison)
6271 Experimental Study of Annular Two-Phase Flow on Rod-Bundle Geometry with Spacer
Son H. Pham, Zensaku Kawara, Takehiko Yokomine, Tomoaki Kunugi (Kyoto Univ)
6285 Research of the Bundle CHF Prediction Based on the Minimum DNBR Point and the BO Point Methods
Wei Liu (Nuclear Power Inst of China), Jianqiang Shan (Xi’an Jiaotong Univ)
6297 Research on Critical Heat Flux of PWR Fuel Assembly in NPIC
Shengjie Qin, Xuemei Lang, Shijie Xie, Junyi Zhang, Wenxing Liu, Wenbin Zhuo (Nuclear Power Inst of China)
6302 Critical Heat Flux Experiment in Internally Heated Vertical Annulus at Low Flow and Low Pressure Conditions
G. Mayer, R. Nagy, I. Nagy (Hungarian Academy of Sciences)
6314 The Sub-Criticality Level Effects in Operational Transients of Beam Interruption in Power and Startup in Accelerator Driven Systems
R. S. do Santos (CNEN/IEN/Inst Nacional de Ciencia)
Track 7: The NURESAFE European Project: Multiscale Thermal Hydraulic Analysis—II
Session Organizer: Elia Merzari (ANL)
9:30 a.m.-12:00 p.m.
6325 DNS of Turbulent Convective Flow Boiling in a Channel
D. Metrailler, S. Reboux, D. Caviezel, D. Lakehal (ASCOMP GmbH)
6335 Three-Dimensional Simulation of Flooding Waves in a Vertical Pipe
M. Tekavčič, B. Končar, I. Kljenak (Jožef Stefan Inst)
6349 Uncertainty Evaluation of CFD Simulation using Optimal Statistical Estimator
A. Prosek, B. Končar, M. Leskovar, S. Košmrlj (Jožef Stefan Inst)
6360 Near-Wall Turbulence-Bubbles Interactions in a Channel Flow at Reτ=400: A DNS/LES investigation
D. Metrailler, S. Reboux, D. Lakehal (ASCOMP GmbH)
6372 CATHARE-TransAT Coupling for the Prediction of Boron Dilution in the Rocom Test Facility
J. Bao, S. Reboux, N. Pagan, D. Lakehal (ASCOMP GmbH)
6384 Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows
Stephane Mimouni, M. Guingo, M. Hassanaly, J. Lavieville, N. Mechitoua, N. Mérigoux (EdF R&D)
Track 7: OECD/NEA Benchmark Study of the Accident at the Fukushima Dai-ichi Nuclear Power Plant—II
Session Organizer: Elia Merzari (ANL)
6401 Analysis of the Fukushima Daiichi NPP Unit 3 with MELCOR_2.1
L. Fernandez-Moguel, A. Rydl, B. Jaeckel (Scherrer Inst)
6412 Thermal Hydraulic and Core Relocation Analysis on Fukushima Daiichi Unit 1
Tae Woon Kim, Sung Il Kim, Jinho Song, KwangSoon Ha, Kwangil Ahn (KAERI)
6425 Effect of External Water Injection on Core Degradation and Fission Product Release in Fukushima Unit 1 Accident
Sung Il Kim, Tae Woon Kim, Kwang Soon Ha, Jinho Song (KAERI)
6435 Recent Findings on the Damaged Reactors and Containment Vessels of Fukushima Dai-ichi NPS
D. Yamada, S. Mizokami, T. Honda, D. Yamauchi, Y. Yamanaka (Tokyo Electric Power Co.)
6452 ATHLET-CD/COCOSYS Analyses of Severe Accidents in Fukushima (Units 2 and 3) within the OECD/NEA BSAF Project, Phase 1
M. Sonnenkalb, S. Band (GRS GmbH)
Track 3: Boiling and Condensation Heat Transfer
Session Organizer: Elia Merzari (ANL)
6466 Assessment of the MELCOR and RELAP5-3D Code for Condensation in the Presence of Noncondensable Gas
Wen Fu (Tsinghua Univ), Dhongik Yoon, Michael L. Corradini, Mark H. Anderson (Univ of Wisconsin, Madison)
6480 Simulations of High-Pressure Subcooled Boiling Flows in Rectangular Channels
R. Thakrar, J. Murallidharan, S. P. Walker (Imperial College London)
6494 Analysis of Wave Influence on Steam Condensation with Non-Condensable Gases Using CFD
Xianmao Wang, Huajian Chang (Tsinghua Univ), Liyong Han (State Nuclear Power Technology R&D Center)
6504 Heat Transfer Regime Calibration for Phase-Change Heat Exchangers in RELAP5-3D
R. P. Martin (B&W mPower, Inc), W. L. Weaver (Consultant)
6517 Integrated Assessment of Thermal Hydraulic Processes in W7-X Fusion Experimental Facility
T. Kaliatka, E. Uspuras, A. Kaliatka (Lithuanian Energy Inst)
6530 Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions
J. Murallidharan, G. Giustini (Imperial College London), Y. Sato, B. Ničeno (PSI), V. Badalassi, S. P. Walker (Imperial College London)
Track 5: Fuel Coolant Interaction, Modeling and Experiments—I
Session Organizer: Elia Merzari (ANL)
6543 A Two-Scale Approach for Modeling the Corium Melt Fragmentation during Fuel-Coolant Interaction
S. Castrillon Escobar, R. Meignen, S. Picchi (IRSN), N. Rimbert, M. Gradeck (LEMTA, Univ)
6557 Influence of Oxidation on Fuel Coolant Interaction
Matjaž Leskovar, Vasilij Centrih (Jožef Stefan Inst)
6569 An Experimental Study on Void Generation Around Hot Metal Particle Quenched into Water Pool
Louis Manickam, Sachin Thakre, Weimin Ma (KTH)
6579 Suppression Measures and Effective Triggering Retardant of Steam Explosions
Masahiro Furuya, Takahiro Arai (CRIEPI)
6590 The Effect of Thermal Conditions and Jet Properties on Steam Explosion
I. Baruch (Ben-Gurion Univ of the Negev), G. Widenfeld (NRCN)
6601 Intensification of Chemically Assisted Melt-Water Explosive Interactions
Anthony A. Sansone, Rusi P. Taleyarkhan (Purdue Univ)
Track 6: Thermal Hydraulics in Sodium-Cooled Fast Reactors (Verification and Validation)—IV
Session Organizer: W. David Pointer, Ph.D. (ORNL)
6614 The Present State-of-the-Art Thermal Striping Studies for Sodium Cooled Fast Reactors
Seok-Ki Choi, Ji-Woong Han, Dehee Kim, Tae-Ho Lee (KAERI)
6625 CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor
A. Kraus, R. Hu (ANL)
6639 Convection Heat Transfer Analysis and Correlation for Alkali Liquid Metals in Uniformly Heated Tubes
Timothy M. Schriener, Mohamed S. El-Genk (Univ of New Mexico)
6650 Benchmark Analysis of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Validation of Fluid-Structure Thermal Interaction Code for Sodium-Cooled FastReactor
Masaaki Tanaka (JAEA), Kazuyoshi Nagasawa (NESI In-Corp)
6664 Proposal of Benchmark Problem of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Code Validation in Sodium-Cooled Fast Reactor Development
J. Kobayashi, M. Tanaka, S. Ohno, H. Ohshima, H. Kamide (JAEA)
6678 CFD Investigation of Wire-Wrapped Fuel Rod Bundles and Flow Sensitivity to Bundle Size
L. M. Brockmeyer, F. S. Sarikurt, Y. A. Hassan (Texas A&M), E. Merzari (ANL)
Track 1: Natural Circulation, Passive Safety Systems and Related Phenomena—II
Session Organizer: Paolo Ferroni (Westinghouse)
6692 Conceptual Design Approach of Passive Cooling Systems
C. Diakodimitris, P. A. Douxchamps, C. Angulo (Tractebel Eng), J. Engelen (SCK/CEN)
6704 Boiled-Up Pool Heat Transfer for a Horizontal Tube Bundle
Robert E. Henry, Kevin Ramsden (Fauske and Assoc), John Freeman, Dan Lee (Exelon)
6717 Natural Circulation Model and Performance Analysis of “SLIMM”—A Small, Modular Reactor
Denise Haskins, Mohamed S. El-Genk (Univ of New Mexico)
6731 Single-Phase and Two-Phase Natural Convection in the McMaster Nuclear Reactor
A. S. Schneider, J. C. Luxat (McMaster Univ)
6745 Temperature Profiles and Mixing in a Natural Circulation Cooling Facility via Distributed Optical Sensors
C. Tompkins, M. Corradini, M. Anderson (Univ of Wisconsin, Madison)
6757 Experimental Investigation of a Scaled Reactor Cavity Cooling System with Air for the VHTR
M. A. Muci (Duke Energy), D. D. Lisowski (ANL), M. H. Anderson, M. L. Corradini (Univ of Wisconsin, Madison)
Track 5: Advanced Design Features for Severe Accident Mitigation
Session Organizer: Elia Merzari (ANL)
6771 Comparison of an Advanced Analytical Tool with the SIMMER Code to Support Astrid Severe Accident Mitigation Studies
N. Marie, A. Bachrata, F. Bertrand (CEA)
6783 Assessment of Molten Pool Cooling Characteristics During LBLOCA for Advanced Passive PWR,
Lili Tong, Ge Shao (Shanghai Jiao Tong Univ)
6793 Analytical Simulation of In-Vessel Retention Strategy for VVER-1000/320 Reactor using MELCOR Code
J. Duspiva (UJV Rez, a. s.)
6807 The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant
J. R. Wang (Natl Tsing Hua Univ/ INER), H. T. Lin (INER), Y. T. Lee, A. L. Ho, S. W. Chen, C. Shih (Natl Tsing Hua Univ)
6821 A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model
Chi-Thanh Tran (Vietnam Atomic Energy Inst), Viet-Hung Nguyen (Hanoi Unive of Science and Technology), Mika Tahara, Yoshihiro Kojima, Ryoichi Hamazaki (Toshiba Corp), Pavel Kudinov (Royal Inst of Technology)
Track 1: Multifield Two-Phase Flow Modeling—I
Session Organizer: Takashi Hibiki (Purdue Univ)
6835 Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model
S. L. Sharma, T. Hibiki, M. Ishii (Purdue Univ), C. S. Brooks (Univ of Illinois), J. P. Schlegel (Missouri Univ Sci Tech), Y. Liu (Virginia Polytechnic Inst and State Univ), J. R. Buchanan (Bechtel Marine Propulsion Corp)
6849 Liquid-Side Interfacial Heat Transfer in Inverted Annular Film Boiling
J. M. Kelly (NRC)
6863 Validation and Cross-Verification of Three Mechanistic Codes for Annular Two-Phase Flow Simulation and Dryout Prediction
L. Sanmiguel Gimeno, S. P. Walker, G. F. Hewitt (Imperial College), J.-M. Le Corre (Westinghouse Electric Sweden), A. Dasgupta (BARC), M. Ahmad (Pakistan Inst of Eng & Applied Sciences)
6876 Numerical Study on Modeling of Liquid Film Flow under Countercurrent Flow Limitation in Volume of Fluid Method
T. Watanabe, T. Takata (Osaka Univ), A. Yamaguchi (Univ of Tokyo)
6890 Development of a Post-Dryout Heat Transfer Model
Y.-J. Wang, C. Pan (Natl Tsing Hua Univ)
6904 Derivation of a Generic Multi-Field Two-Fluid Model
Y. Liu (Virginia Tech), J. D. Talley, K. J. Hogan, J. R. Buchanan, Jr. (Bechtel Marine Propulsion Corp.)
Track 6: Thermal Hydraulics in Salt-Cooled High-Temperature Reactors
Session Organizer: Elia Merzari (ANL)
6918 Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing
N. Haneklaus, J. Kendrick, L. Huddar, N. Zweibaum, P. F. Peterson (Univ of California, Berkeley), J. Hughes, E. Blandford (Univ of New Mexico), Q. Lv, X. Sun (Ohio State), G. Yoder (ORNL)
6931 Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor
Chenglong Wang, Kaichao Sun, Lin-Wen Hu (MIT), Suizheng, Qiu, Dalin Zhang (Xi’an Jiaotong Univ)
6945 Pseudo-3D Steady State Thermal-Hydraulic Modeling of the Advanced High Temperature Reactor Fuel Assembly
P. Avigni, B. Petrovic (Georgia Tech)
6959 Disturbed Transient Analysis with Stable Operation Mode of TMSR-SF1
Minghai Li, Jie Zhang, Yang Zou, Yao Fu, Yang Yang (Shanghai Inst of Applied Physics/CAS)
Thursday, September 3, 2015
1:30-3:35 p.m.
Track 7: Addressing the GSI-191: Progress in Methodologies and Technologies—II
Session Organizer: Elia Merzari (ANL)
6969 RoverD: Use of Test Data in GSI-191 Risk Assessment
Ernie Kee (Texas A&M), John Hasenbein, Alex Zolan (Univ of Texas, Austin), Phil Grissom (SNC), Seyed Reihani (Univ of Illinois, Champaign), Fatma Yilmaz (South Texas Project), Bruce Letellier (Alion Sci Technol), Vera Moiseytseva (YK.risk, LLC), David Imbaratto (PG&E Diablo Canyon Power Plant)
6983 MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191
B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan (Texas A&M)
6998 A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models
B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan (Texas A&M)
7011 Unique Challenges in Making a Regulatory Decision Regarding the Combined Effects of Boric Acid Precipitation and GSI-191
Ashley Guzzetta (NRC)
7021 Viscous Inertial Shear-Transition-Adaptive (VISTA) Porous Media Head-Loss Formulation
Bruce Letellier, Mark Macali (Alion Sci Technol), Ernie Kee (Texas A&M)
Track 7: OECD/NEA Benchmark Study of the Accident at the Fukushima Dai-ichi Nuclear Power Plant—III
Session Organizer: Elia Merzari (ANL)
7033 Overview and Outcomes of Benchmark Study of the Accident at the Fukushima Daiichi NPS (OECD/NEA BSAF Project)
Fumihisa Nagase (JAEA), Randall O. Gauntt (SNL), Masanori Naito (The Inst of Applied Energy)
7046 Analysis of Fukushima Unit 2 Accident by Considering the Operating Condition of RCIC System and Torus Room Flooding
Sung Il Kim, Jong-Hwa Park, Kwang Soon Ha, Jinho Song (KAERI)
7055 MAAP-MELCOR Crosswalk Phase 1 Study
David L. Luxat, Joshua T. Hanophy (ERIN Eng and Research, Inc.), Donald Kalanich, Randall O. Gauntt (SNL), Richard M. Wachowiak (EPRI), invited
7071 EPRI MAAP5 Fukushima Daiichi Analysis
David L. Luxat, Jeff R. Gabor (ERIN Eng and Research, Inc.), Richard M. Wachowiak, Rosa L. Yang (EPRI)
7087 The Findings Obtained During the OECD/NEA BSAF Activity with the Employment of the SAMPSON Code
M. Naitoh, M. Pellegrini, A. Takahashi, H. Mizouchi, H. Suzuki (Inst of Applied Energy)
Track 7: CASL—Thermal-Hydraulics Activities in the Consortium for Advanced Simulation of LWRS
Session Organizer: Elia Merzari (ANL)
7101 Mechanistic Modeling of Two-Phase Flow Around Spacer Grids with Mixing Vanes
B. M. Waite, D. R. Shaver, M. Z. Podowski, (RPI)
7115 Interface Tracking Simulations of Bubbly Flows in the PWR Relevant Geometries
Jun Fang (NCSU), Michel Rasquin (ANL), Igor A. Bolotnov (NCSU)
7129 Spectral Analysis of the Turbulent Energy Spectrum in Single and Two-Phase Bubbly Flows in Different Geometries Based on Direct Numerical Simulation Results
C. S. Brown, I. A. Bolotnov (NCSU)
7143 Synthesis of CRUD and its Effects on Pool and Subcooled Flow Boiling
Carolyn Coyle, Jacopo Buongiorno, Thomas McKrell, Robert Cohen (MIT)
7154 CTF Validation Activities
T. Blyth, C. Dances, M. Avramova (Penn State), R. Salko (ORNL)
Track 5: Fuel Coolant Interaction, Modeling and Experiments—II
Session Organizer: Elia Merzari (ANL)
7168 An Explanation of BORAX-1, SPERT-1 and the SL-1 Accident
Robert E. Henry (Fauske & Assoc), Michael Epstein (Fauske and Associates (Retired)), Hans K. Fauske (Fauske and Assoc)
7182 Simulation of FARO L-28 and L-31 Tests to Assess Molten Jet Fragmentation Modeling in MAAP
A. Le Belguet, E. Beuzet, M. Torkhani (EdF R&D)
7196 Heat Transfer Origin of Thermal Shock Fracture and Its Application for LWR Fuel during Reflood
Youho Lee, Hee Cheon No (KAIST)
7208 Simulation of Ex-Vessel Melt Jet Breakup and Sensitivity on Model Parameters and Accident Conditions
Kiyofumi Moriyama, Hyun Sun Park (POSTECH)
7222 Development of TEXAS-V Code Surrogate Model for Assessment of Steam Explosion Impact in Nordic BWR
D. Grishchenko, S. Basso, S. Galushin, P. Kudinov (KTH)
Track 3: Validation & Verification: General
Session Organizer: Xiaodong Sun (Ohio State)
7236 Validation Test Plan of a CANDU-6 Moderator Tank Scaled-Down Test Facility
Bo W. Rhee, Hyoung T. Kim (KAERI), Michael D. Atkins, Tongbeum Kim (Univ of Witwatersrand)
7249 Thermal Cycling Testing of Distributed Fiber Optic Temperature Sensors for High-Temperature Applications
Darius D. Lisowski, Craig D. Gerardi, Stephen W. Lomperski (ANL)
7261 Assessment of RELAP5/MOD3.3 for Subcooled Boiling, Flashing and Condensation in a Vertical Annulus
Caleb S. Brooks (Univ of Illinois), William D. Fullmer (Univ of Colorado), Clayton D. Lietwiler (GSE Systems Inc.)
7272 Initial Condition Effects on Kelvin-Helmholtz Instabilities and Development of a Round Jet
Amy B. McCleney, Philippe M. Bardet (The George Washington Univ)
7286 Experimental Investigation on Transient Heat Transfer Characteristics of C-Shape Heating Rod Bundle used in PRHR HX
Yuhao Zhang, Daogang Lu, Guanghao Wu (North China Electric Power Univ), Zheng Du (State Nuclear Power Software Development Center of China)
Track 1: Two-Phase Flow and Heat Transfer Fundamentals—VI
Session Organizer: Annalisa Manera (Univ of Michigan)
7297 Interfacial Stability in Vertical Swirling Annular Two-Phase Flow
Li Liu, Bofeng Bai (Xi’an Jiaotong Univ)
7312 Boiled-Up Level and Boiling Two-Phase Flow Dynamics in 5x5 Heated Rod Bundle during Boil-Off Process under Atmospheric Pressure Conditions
Takahiro Arai, Masahiro Furuya, Taizo Kanai, Kenetsu Shirakawa, Yoshihisa Nishi (CRIEPI)
7323 Pulsed Injection Tracer Mixing in Annular Liquid Films
A. Saxena, J. Eiholzer, H.-M. Prasser (ETH Zurich)
7337 Heat Transfer from Finned Surface in Downward-Facing Subcooled Flow Boiling
Abdul R. Khan, Nejdet Erkan, Koji Okamoto (Univ of Tokyo)
7347 Quenching of a Heated Rod: Physical Phenomena and Heat Transfer
Arnab Dasgupta, P. P. Kulkarni, G. J. Gorade, D. K. Chandraker, A. K. Nayak, P. K. Vijayan (BARC), S. P. Walker (Imperial College, London)
Track 5: Modeling and Experiments of Severe Accidents—V
Session Organizer: Elia Merzari (ANL)
7358 Numerical Simulation of Anisotropic Ablation of Siliceous Concrete—Analysis of CCI-3 MCCI Experiment by MPS Method
Xin Li, Akifumi Yamaji (Waseda Univ)
7372 The Energetics of Coolant-Bubble-Covergas Interactions Associated with LMR Out-Of-Reactor Source Term Experiments
John C. Petrykowski, Hmza Mohamed (Univ of Dayton)
7386 RCIC Governing Equation Scoping Studies for Severe Accidents
Kyle Ross, Jeffrey Neil Cardoni (SNL)
7401 Analysis of Metal Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method
Daisuke Masumura (Waseda Univ), Yoshiaki Oka (Tokyo Univ), Akifumi Yamaji (Waseda Univ), Masahiro Furuya (CRIEPI)
Track 6: Thermal Hydraulics in Lead-Cooled and Lead-Bismuth-Cooled Fast Reactors
Session Organizer: W. David Pointer, Ph.D. (ORNL)
7414 European Outlook for LMFR Thermal Hydraulics
F. Roelofs, A. Shams (NRG), J. Pacio (KIT), V. Moreau (CRS4), P. Planquart (VKI), K. van Tichelen (SCK/CEN), I. Di Piazza, M. Tarantino (ENEA)
7426 Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop
Sheng Gao, Liuli Chen, Kefeng lv, Chenchong Yue, Qunying Huang, Yican Wu (Chinese Academy of Science/Jiangsu Higher Education Inst), Mariano Tarantino (ENEA)
7434 Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS
Tianyu Lu, Jianqiang Shan, Junli Gou, Bin Zhang, Bo Zhang, Li Ge, Yuan Yuan, Zijiang Yang (Xi’an Jiaotong Univ)
7448 Experimental and Numerical Investigations of Interaction Between Heavy Liquid Metal and Water for Supporting the Safety of LFR GEN. IV Reator Design
A. Del Nevo (ENEA), N. Giannini, A. Pesetti, N. Forgione (UNIPI)
7462 Experimental and Numerical Investigation of Double Wall Bayonet Tubes Performances in Pool Type Integral Test Facility
D. Rozzia (Univ of Pisa), A. Del Nevo, M. Tarantino (ENEA)
Track 6: Thermal Hydraulics in Supercritical Water Reactors
Session Organizers: Martin Rohde (Udelft), Xiaojing Liu (SJTU)
7472 Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2x2 Rod Bundles
M. Zhao (Shanghai Jiao Tong Univ/KIT), H. Y. Gu (Shanghai Jiao Tong Univ), X. Chang (Shanghai Jiao Tong Univ/KIT), H. B. Li (China Nuclear Power Technology Research Inst), Q. R. Yang (KIT)
7486 CFD Simulation of Supercritical Flow and Heat Transfer in a Three Rod Wire Wrapped Bundle
K. Podila, Y. F. Rao (Canadian Nuclear Lab)
7496 Development Heat Transfer Correlations for Supercritial CO2 in Natural Circulation Loop
Guangxu Liu, Yanping Huang, Junfeng Wang (Nuclear Power Inst of China)
Thursday, September 3, 2015
4:00-6:30 p.m.
Track 7: Corium Research Platform: Past and Future—II
Session Organizer: Elia Merzari (ANL)
7505 FCI Test Results Under Conditions of the Partially Flooded Cavity and the Flooded Reactor in the TROI
S. W. Hong, Y. S, Na, S. H. Hong, J. H. Song, (KAERI)
7518 Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident
Jacquemain Didier, Vola Didier, Meignen Renaud, Jean Michel Bonnet, Fichot Florian, Raimond Emmanuel, Marc Barrachin (IRSN)
7537 Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Melt Spreading
M. T. Farmer (ANL), K. R. Robb, M. W. Francis (ORNL)
7552 Corium-Related Improvements in the EDF Version of MAAP Code in the Frame of Severe Accident Studies
E. Beuzet, N. Bakouta, M. Boissavit, F. Haurais, A. L. Belguet, V. Lombard, M. Torkhani (EdF R&D)
7568 VESTA Test Facility for Severe Accident Researches at KAERI
Hwan Yeol Kim, Sang Mo An, Jaehoon Jung, Kwang Soon Ha, Jin Ho Song (KAERI)
7578 Core Melt Stabilization Concepts for Existing and Future LWRs and Associated R&D Needs
Manfred Fischer (AREVA GmbH), Sevostian V. Bechta (KTH), Vladimir V. Bezlepkin (ATOMPROECT Enterprise of ROSATOM State Corp), Ryoichi Hamazaki (Toshiba Corp), Alexei Miassoedov (KIT)
Track 8: Advancements in the Prediction of DNB with CFD–Panel
Session Organizer: Emilio Baglietto (MIT)
7593 Computational Multi-Fluid Dynamics Predictions of DNB
S. Mimouni (EdF R&D)
7608 Use of CFD to Predict Critical Heat Flux in Rod Bundles
Z. E. Karoutas, Y. Xu, L. David Smith III, P. F. Joffre, Y. Sung (Westinghouse)
Track 7: Design, Analysis and Testing of Micro-, Mini and Other Small-Diameter Channel Heat Exchangers
Session Organizer: Elia Merzari (ANL)
7621 Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger
Minghui Chen, Xiaodong Sun, Richard N. Christensen (Ohio State), Isaac Skavdahl, Vivek P. Utgikar (Univ of Idaho), Piyush Sabharwall (INL)
7637 Printed Circuit Heat Exchanger Design, Analysis and Experiment
Seungjoon Baik, Seong Gu Kim, Seongmin Son, Hyeon Tae Kim, Jeong Ik Lee (KAIST)
7647 Modeling the Mechanical Integrity of Airfoil Printed Circuit Heat Exchangers
Ian Jentz, Mark Anderson (Univ of Wisconsin, Madison), Xiaodong Sun (Ohio State)
7658 CFD Modeling of Sodium-Oxide Deposition in Sodium-Cooled Fast Reactor Compact Heat Exchangers
E. Tatli, J. P. Mazzoccoli, P. Ferroni (Westinghouse)
7673 Preliminary Structural Assessment of a Printed Circuit Heat Exchanger with S-Shaped Fins
X. Zhang, X. Sun, R. N. Christensen (Ohio State), M. Anderson (Univ of Wisconsin, Madison)
7687 Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger
F. Vitillo, X. Jeanningros, L. Cachon, C. Galati, P. Olympio, S. Madeleine (CEA Cadarache)
Track 1: Flow-Induced Vibration in Reactor Components
Session Organizer: Wade R. Marcum (Oregon State Univ)
7701 Comprehensive Characterization of Motion of a Helical Structure Due to Flow Induced Vibration
P. L. Harmon, W. R. Marcum (Oregon State Univ)
7714 Impact of Flow Induced Vibration Acoustic Loads on the Design of the Peach Bottom Replacement Steam Dryer
David R. Forsyth, Leslie F. Wellstein, Robert C. Theuret, David A. Suddaby (Westinghouse), John Rommel, Ken Ainger (Exelon Generation Co.)
7725 Numerical Prediction of Flow Induced Vibrations in Nuclear Reactor Applications
E. ter Hofstede (NRG/TU Delf) A. Shams (NRG), A. H. van Zuijlen (TU Delft)
7736 Symbolic Dynamics Applied in the Identification of Flow Patterns Inside Tube Banks
Alexandre Vagtinski de Paula, Sergio Viçosa Möller, (UFRGS)
7749 Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles
Noah A. Weichselbaum, Shadman Hussain, Pierre Korysko, Morteza Rahimi-Abkenar, Philippe M. Bardet, Majid T. Manzari (The George Washington Univ)
Track 2: Computational Fluid Dynamics—IV
Session Organizer: Si Young Lee (SRNL)
7764 CFD Analysis of Flowing Field in 5x5 Rod Bundle with Multi-Grids
J. B. Zhao, X. Y. Zhang, L. Qiao (South China Univ of Technology)
7776 Towards the Development of a Full-Scale Transient CFD Model to Simulate the Static and Dynamic in-Core Mass Flux Distribution in a Classical German PWR
Dong-Yuan Sheng (Westinghouse Electric Sweden AB), Marcus Seidl (E.ON Kernkraft GmbH)
7792 A Review of AREVA’s Experimental Validation of State-of-the-Art Single-Phase CFD Methods with Application to PWR Fuel Analysis and Design
A. Hatman, A. Chatelain, K. Goodheart, M. Martin, T. Keheley (AREVA Inc.)
7806 Computational Fluid Dynamics Analysis of the Fluid Flow and Heat Transfer in the Core Bypass Region of a PWR
I. Clifford, A. Vasiliev, O. Zerkak, H. Ferroukhi, A. Pautz (Paul Scherrer Inst)
7820 Single-Phase and Two-Phase CFD Simulations of the Coolant Flow Inside a Bruce/Darlington CANDU Flow Channel
F. Abbasian, G. I. Hadaller, R. A. Fortman (Stern Laboratories Inc.)
7830 Computational Fluid Dynamics Benchmark using AP1000® 1/4-Scale Upper Head Test Data
William L. Moody, Teresa A. Bissett, Yiban Xu, Gregory A. Meyer (Westinghouse)
Track 6: Thermal Hydraulics in High-Temperature Gas-Cooled Reactors—I
Session Organizer: Dr. Elia Merzari (ANL)
7844 Analysis on Anticipated Transient Without SCRAMS (ATWS) Accidents of the HTR-10GT
Minggang Lang, Yujie Dong (Tsinghua Univ)
7858 Analyses of LOCAs in the Primary Heat Transfer System of the Helium Cooled Pebble Bed Blanket Concept
Bruno Gonfiotti, Sandro Paci (Univ of Pisa), Dario Carloni, Lorenzo V. Boccaccini (KIT)
7872 Numerical Solution of Heat Transfer Process in a Prismatic VHTR Considering Core Bypass Flow and Cross Flow
Li Wang, Qiusheng Liu, Katsuya Fukuda (Kobe Univ)
7886 Modeling of the Thermal Hydraulics of Very-High-Temperature Reactors with the System Code ATHLET
D. von der Cron, H. V. Hristov, A. Seubert (GRS)
7900 Concept Design and Thermal-Hydraulic Analysis for Helium-Cooled ADS
Tianji Peng, Zhiwei Zhou, Xuanyu Sheng (Tsinghua Univ), Long Gu (Chinese Academy of Sciences)
7913 Study of Abnormal Heat Transfer during Forced and Natural Convection Scenarios in a Prismatic Core of a VHTR: Numerical and Experimental Results
Francisco I. Valentin, Narbeh Artoun (City College of New York), Ryan Anderson (Montana State Univ), Masahiro Kawaji (City College of New York/The CUNY Energy Inst)
Track 2: Computational Thermal-Hydraulics: General
Session Organizer: Elia Merzari (ANL)
7927 Improvement and Validation of the Wall Heat Transfer Package of RELAP5/MOD3.3
Xiaofei Xiong, Jianqiang Shan, Junli Gou (Xi’an Jiaotong Univ)
7941 Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel
Yingwei Wu, Qing Lu, Yangbin Deng, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (Xi’an Jiaotong Univ)
7954 Computational Analysis of Bubble Micro-Layer in Sub-Cooled Boiling
Eyitayo James Owoeye, DuWayne Schubring (Univ of Florida)
7967 On the Application of Wall Boiling Models to Prediction of Subcooled Flow Boiling using EAGLE Code
N. H. Hoang, I. C. Chu, D. J. Euh, C. H. Song (Korea Univ of Science and Technology/KAERI)
7981 CFD Analyses of Main Flow Penetration Depth in Isolated Branch Lines
Brandon LaFleur, Victor Petrov, Annalisa Manera (Univ of Michigan)
7993 Fluid-Structure Interaction (FSI) Modeling of Thin Plates
C. J. Jesse, J. C. Kennedy, G. L. Solbrekken (Univ of Missouri, Columbia)
Track 5 Modeling and Experiments of Severe Accidents—VI
Session Organizer: Elia Merzari (ANL)
8007 Methodology using MELCOR2.1/SNAP to Establish an SBO Model of Chinshan BWR/4 Nuclear Power Plant
Yu Chiang (Natl Tsing Hua Univ), Jong-Rong Wang (Natl Tsing Hua Univ/Nuclear and New Energy Education and Research Foundation), Hao-Tzu Lin (INER), Shao-Wen Chen (Natl Tsing Hua Univ), Chunkuan Shih (Natl Tsing Hua Univ/Nuclear and New Energy Education and Research Foundation)
8021 Simulation of Orientation Effects on Critical Heat Flux in Downward-Facing Channel for IVR
K. Shirvan, R. Azizian (MIT)
8035 Severe Accident Progression in the BWR Lower Plenum and the Modes of Vessel Failure
B. R. Sehgal, S. Bechta (KTH)
8046 Experimental Investigation of Debris Bed Agglomeration and Particle Size Distribution using WO3-ZRO2 Melt
Paval Kudinov, Dmitry Grishchenko, Alexander Konovalenko, K. Karbojian (KTH), S E. Yakush (RAS)
8055 Experiments and Modeling of Particulate Debris Spreading in a Pool
A. Konovalenko (KTH), S. Basso, P. Kudinov (KTH)
Track 1: Fundamental Thermal-Hydraulics: GeneraI—II
Session Organizer: Xiaodong Sun (Ohio State)
8069 Large Scale BWR Containment LOCA Response Test at the INKA Test Facility
Thomas Wagner (AREVA GmbH), Stephan Leyer (Univ du Luxembourg)
8080 Blind and Aftermath Numerical Analyses of Supercritical Water Flow and Heat Transfer in 1/12 of 7-Rod Bundle with Spacers
P. Mühlbauer, O. Frybort, K. Gregor (Research Centre Rez)
8092 Numerical Simulation of Supercritical Pressure Fluids with Variable Turbulent Prandtl Number and Modified Damping Function (1/2)
Y. Y. Bae, E. S. Kim, M. H. Kim (KAERI)
8106 Computational Fluid Dynamics Assessment of Emergency Core Cooling System Check Valves at Comanche Peak
Brian M. Golchert, Thomas Loebig, James Wyble III (Westinghouse), Andrea Lemons (Luminant)
8116 Numerical Simulation on Melting and Solidification Based on Lagrangian Approach
Jin-Biao Xiong, Hong-Yan Wang, Xu Cheng, Yan-Hua Yang (Jiao Tong Univ)
Friday, September 4, 2015
8:00-9:00 a.m.
Friday Keynote Session—X
8129 Status and Challenges of Nuclear Thermal-Hydraulics Research in China
X. Cheng (KIT/SNPRI), Y. H. Yang (SJTU/SNPRI)
Friday Keynote Session—XI
8141 Progress of Thermal Hydraulic Evaluation Methods and Experimental Studies on a Sodium-Cooled Fast Reactor and Its Safety
H. Kamide, H. Ohshima, T. Sakai, M. Tanaka (JAEA)
Friday Keynote Session—XII
8156 U.S. DOE Severe Accident Research Following the Fukushima Daiichi Accidents
M. T. Farmer (ANL), M. Corradini (Univ of Wisconsin, Madison), J. Rempe (Rempe and Assoc, LLC), R. Reister, D. Peko (DOE)
Friday, September 4, 2015
9:30-12:00 p.m.
Track 7: Critical Heat Flux in Fuel Bundle: Modeling, Prediction and Experimental Measurements—II
8165 Critical Heat Flux with Subcooled Flowing Water in Tubes for Pressures from Atmosphere to Near-Critical Point
Y. Chen, K. Bi, C. Yang, M. Zhao, K. Du (China Institute of Atomic Energy)
8177 A Consideration of Experimental Uncertainties for Predicting CHF in Rod Bundles
Dae-Hyun Hwang, Seong-Jin Kim, Hyuk Kwon, Kyong-Won Seo (KAERI)
8189 Study on CHF Correlation for PWR at Low Pressure Conditions Based on Stepwise Regression Analysis
Yin Yuan (Shenzhen Univ), Fu Xian-Gang (CNPRI), Zhu Yuanbing, Kong Xiangyin, Li JingGang (CNPRI)
8201 Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly
Hui Zhang, Bao-Wen Yang, Bin Zhang, Bin Han (X'an Jiaotong Univ), Yanping Huang (CNNC)
8212 Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments
Aiguo Liu, Bao-Wen Yang, Sipeng Wang, Yudong Zha (Xi’an Jiaotong Univ)
8226 Improvement of Mixing Vane Crossflow Model in Subchannel Analysis
Hu Mao, Bao-Wen Yang, Jianqiang Shan, Bo Zhang (Xi’an Jiaotong Univ)
Track 7: Advances in System Thermal-Hydraulics Modeling and Code Development
Session Organizer: Elia Merzani
8237 A Strongly Coupled Reactor Core Isolation Cooling System Model for Extended Station Blackout Analyses
Haihua Zhao, Ling Zou, Hongbin Zhang, Richard C. Martineau (INL)
8251 Development of a Multiple Liquid Component Capability in GOTHIC to Better Support Boric Acid, Radiological, and GSI-191 Analyses
J. W. Lane, T. L. George (Numerical Application)
8265 Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code
S. M. Bajorek, M. Bernard, C. Gingrich, C. L. Hoxie, A. Ireland, J. Kelly, J. Mahaffy, C. Murray, J. Spore, J. Staudenmeier, M. Thurgood, K. Tien, J. Whitman (NRC)
8279 Development of a Coupled Code System Based on SPACE Safety Analysis Code and RAST-K Three-Dimensional Neutronics Code
Seyun Kim, Eunki Lee, Yo-Han Kim, Dong-Hyuk Lee (Central Research Inst/Korea Hydro & Nuclear Power Co.)
8293 Recent Developments for the SAS4A/SASSYS-1 Safety Analysis Code
T. H. Fanning, J. W. Thomas, T. Sumner, A. J. Brunett (ANL)
8305 Recent Improvements in the SPACE Code
Kyung Doo Kim, S. W. Lee, S. W. Bae, B. J. Kim, J. S. Heo, J. H. Lee, B.U. Bae, B. D. Chung (KAERI)
Track 1: Boiling and Condensation Fundamentals—III
Session Organizer: Caleb S. Brooks (Univ of Illinois)
8319 Condensation Heat Transfer Coefficient Correlation based on Slip Ratio Model in a Horizontal Heat Exchanger
Seok Kim, Sung Uk Ryu, Seung Tae Lee, Dong-Jin Euh, Chul-Hwa Song (KAERI)
8331 Direct Condensation and Entrainment Steam Experiments at the TOPFLOW-DENISE Facility
T. Seidel, M. Beyer, D. Lucas (Helmholtz-Zentrum Dresden-Rossendorf)
8339 Experimental Study of Boiling Initiation on a Smooth Heating Surface
Hang Jin Jo, Moriyama Kiyofumi, Hyunwoo Noh, Hyun Sun Park (POSTECH), Moo Hwan Kim (POSTECH/KINS)
8347 A Generalized Correlation for Steam Condensation Rates in the Presence of Air-Helium Mixture
A. Dehbi (Scherrer Inst)
8360 Wall Superheat Prediction in Narrow Rectangular Channels Under Fully Developed Boiling of Water at Low Pressures
A. Ghione, P. Vinai, C. Demaziere (Chalmers Univ of Techn), B. Noel (CEA)
8374 Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas
F. X. Buschman, D. L. Aumiller (BAPL), L. E. Hochreiter, F. B. Cheung, D. K. Johnson, M. J. Meholic, D. J. Skilone (Penn State Univ)
Track 2: Computational Fluid Dynamics—V,
Session Organizer: Si Young Lee (SRNL)
8386 Numerical Analysis of Influence of Branch Flow on Thermal Mixing in a T-Junction Piping System
Karthick Selvam, Rudi Kulenovic, Eckart Laurien (Univ of Stuttgart)
8400 Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat
Sungje Hong, Kunwoo Yi, Jin Huh, Inyoung Im, Eunkee Kim (KEPCO Engineering and Construction Co.. Inc.)
8412 A Structure-Based Approach for Topological Resolution of Coherent Turbulence: Overview and Demonstration
Giancarlo Lenci, Emilio Baglietto (MIT)
8426 CFD Analysis of Turbulent Mixed Convection Upward Flow of Supercritical Water in a Vertical Tube
Vladimir Agranat (Applied Computational Fluid Dynamics Analysis), Michael Malin (Concentration, Heat and Momentum Limited), Rand Abdullah, Igor Pioro (Univ of Ontario Inst of Tech)
8440 Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel
Yu-Ting Ku, Yung-Shin Tseng, Jung-Hua Yang, Shao-Wen Chen, Jong-Rong Wang, Chunkuan Shin (Natl Tsing Hua Univ)
8454 Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow
Kai Wang, Rong Cai, Wuyue Ren, Suizheng Qiu, Wenxi Tian, G.H. Su, Ronghua Chen (Xi’an Jiaotong Univ)
Track 6: Thermal Hydraulics in High-Temperature Gas-Cooled Reactors—II
Session Organizer: W. David Pointer, Ph.D. (ORNL)
8466 Heat and Dust Transport in a Pebble Bed HTR
Jayaraju, S.T., Shams, A., Roelofs, F. (NRG)
8480 An Experimental Investigation of Thermal Loading on a Plate from Parallel Triple Jet
Paul J. Kristo, D. Tyler Landfried, Mark L. Kimber (Univ of Pittsburgh)
8492 Effect of End Plate on the Flow Crossing a Yawed Circular Cylinder
Hui Liang, Sheng-Yao Jiang, Ri Qiang Duan (Tsinghua Univ)
8506 Analytical Modeling of a Scaled Reactor Cavity Cooling System (RCCS) with Air
Y. Aharon (Nuclear Research Center Negev), M. Muci, C. Tompkins, M. Anderson, M. Corradini (Univ of Wisconsin, Madison)
8519 Role of Radiation Heat Transfer in Cooling of a Scaled Model of a Prismatic Graphite Core in a VHTR
Francisco Ivan Valentin, Masahiro Kawaji (City College of New York)
8533 Uncertainty Quantification of Calculated Temperatures for Advanced Gas Reactor Fuel Irradiation Experiments
Binh T. Pham, Grant L. Hawkes, Jeffrey J. Einerson (INL)
Track 1: Natural Circulation, Passive Safety Systems and Related Phenomena—III
Session Organizer: Paolo Ferroni (Westinghouse)
8547 Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility
Thomas Geissler, Uwe Hemple (Technische Univ Dresden), Rita Szijarto (Scherrer Inst), Matthias Beyer (Helmholtz Zentrum Dresden Rossendorf (HZDR)), Horst-Michael Prasser (Scherrrer Inst), Stephan Leyer (technische Hochschule Deggendorf), Markus Walther (AREVA GmbH)
8561 Experimental Investigation and Flow Visualization of Steam Condensation in a Scaled IRWST-ADS Simulator
Suleiman Al Issa, Raphael Macian-Juan (Technische Univ Muchen), Gonzalo Jiminez, Cesar Queral, Javier Monero-Mayorga (Univ Politecnica Madrid)
8575 Investigation of Operational Charactistics of Passive Containment Cooling System for an Advanced PWR
Zheng Huang, Huimin Zhang, Weimin Ma, Qiaoyan Chen, Xiaofeng Han (China Nuclear Power Engineering Co., Ltd.)
8589 CFD Simulation of Natural Convection Cooling After a Loss-of-Flow Transient
A. Kraus, R. Hu (ANL)
8603 Natural Convective Heat Transfer from a Heated Slender Vertical Tube in a Cylindrical Tank
Lin Xian, Guangming Jiang, Hongxing Yu (Nuclear Power Inst of China)
Track 7: Research Progress of Large Advanced PWR Program in China
Session Organizer: Dr. Elia Merzari (ANL)
8616 Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA
S.Z. Qiu, D.C. Sun, W. Tian, Y. Xiang, G.H. Su (Xi’an Jiao Tong Univ), P. Zhang (SNPTRD)
8630 ADS-IRWST Transient Evaluation Model for AP1000 SBLOCA Analysis
Han Wang (State Nuclear Power Technology R&D Center), Peipei Chen (State Nuclear Power Technology Corp)
8643 Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle
Jiangtao Yu, Di Lin Liu, Wenxi Tian, M. Y. Zheng, Yingwei Wu, G. H. Su, S. Z. Qiu (Xi’an Jiaotong Univ)
8657 Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas
Cheng Li, Zhan Gao, Shan Zhou, Hongsen Li, Wangfang Du, Wei Zhao, Lin Yang (Chinese Nuclear Power Technology Corp. R&D Centre)
8669 Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water
Z.W. Wang, W. X. Tian, J. T. Yu, D. L. Zhang, G. H. Su, S. Z. Qiu, R.H. Chen (Xi’an Jiao Tong Univ), B. Dong (State Nuclear Power Software Development Center)
8683 Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition
W. Y. Ren, G.J. Yu, J.W. Bian, W.X. Tian, G.H. Su, S.Z. Qiu (Xi’an Jiao Tong Univ), X.L. Fu (SNPSDC/NKLNPS)
Track 1: Multifield Two-Phase Flow Modeling—II
Session Organizer: Takashi Hibiki (Purdue Univ)
8695 Film-Droplet Split Correlation at the Onset of Annular-Mist Flow
S. Oh, B. Hizoum, P. Saha , B. Dooies, D. Miranda (GE Hitachi Nuclear), J. G. M. Andersen (Consultant)
8707 Numerical Calculation of the Heat Transfer Characteristics of Fuel Cladding with Dirt at Low Coolant Speed
S. H. Yin, X. Y. Zhang, A. Q. Liu (South China Univ of Techn)
8720 Modifications of Critical Heat Flux Models on Horizontal Surfaces in Pool Boiling Using Interfacial Instabilities of Viscous Potential Flows
Jong Hyuk Lee, Byung Jae Kim, Kyung Doo Kim (KAERI)
8732 Analysis and Applications of a Generalized Multi-Field Two Fluid Approach for Plunging Jet Configuration
E. Krepper, D. Lucas (Helmholtz-Zentrum Dresden-Rossendorf), F. Zidouni (USTHB)
8744 Effect of Viscosity on a Well-Posed One-Dimensional Two-Fluid Model for Wavy Two-Phase Flow Beyond the Kelvin-Helmholtz Instability: Limit Cycles and Chaos
Martin Lopez de Bertodano (Purdue Univ), William D. Fullmer (Univ of Colorado, Boulder)
8757 On Well-Posedness and Stability of the Two-Fluid Model for Vertical Bubbly Flows
A. Vaidheeswarn, M. Lopez de Bertodano (Purdue Univ), W. D. Fullmer (Univ of Colorado, Boulder)
Track 2: Plant System Code Development
Session Organizer: Tomasz Kozlowski (Univ of Illinois)
8768 Description of an Improved Turbomachinery Model to be Developed in the CATHARE3 Code for Astrid Power Conversion System Application
G. Mauger, F. Bentivoglio, N. Tauveron (CEA)
8782 Improvement of RELAP5 Models for Condensation of Steam and Steam-Gas Mixture in Horizontal and Inclined Tubes
P. Kral (UJV Rez, a. s.)
8796 Analysis of Protected RIA and LOFA in Plate Type Research Reactor Using Coupled Neutronics Thermal-Hydraulics System Code
Marat Margulis, Erez Gilad (Ben-Gurion Univ of the Negev)
8809 ASTEC Simulation of a SBO with Re-Flood in a German KONVOI NPP
Florian Gremme, Marco K. Koch (Ruhr-Univ Bochum)
8822 Commercial Grade Dedication of RELAP5-3D©
D. Prelewicz (Information Systems Laboratories, Inc.), B. Wolf, C. Delfino (NuScale Power, LLC.)
8831 Evaluation of Thales Subchannel Code Behavior for Loss of Flow and RCP ROTOR Seizure Scenarios
Kang Hoon Moon (KNFC), Erdal Ozdemir (KINGS), Seung J. Oh (KEPCO INGS), Yongdeog Kim (KHNP CRI)