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The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics

Business Conference - The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics
Business Conference

By : Canadian Nuclear Society

Date : 2011

Location : Canada / Toronto

PDF 5771p
Description :

NURETH-14 gathered industry researchers and practitioners engaged in engineering and scientific work focused on nuclear reactor thermalhydraulics. This was the only major conference series devoted solely to the advancement of knowledge in the nuclear reactor thermalhydraulics field.

Keywords :

thermalhydraulics, nuclear reactor, Two-Phase Flow, Heat Transfer Fundamentals, Pressurized Thermal Shock, Thermal Hydraulic conference proceedings

Keywords inside documents :

reactor ,temperature ,nuclear ,figure ,pressure ,model ,water ,transfer ,phase ,thermal ,toronto ,power ,liquid ,nureth ,bubble ,velocity ,international ,steam ,number ,analysis

Product/ documentation details
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics

Product Type : Business Conference

Author : Canadian Nuclear Society

PDF 5771p

Languages : English

The proceedings include: Lessons Learned from the Fukushima Accident, Issues and Future Directions of Thermalhydraulics Research and Development, as well as Global Cooperation in Nuclear Education and Research; these panel sessions brought together an international group of panelists from all over the world.

 

NURETH-14 was a unique opportunity for researchers and practitioners in the field to present results of their work and to discuss challenges and new ideas with attendees.

 

Topics were : 

  • Two-Phase Flow and Heat Transfer Fundamentals
  • Code Developments and Applications
  • Severe Accidents and Fires
  • Advanced Code Developments
  • Operation and Safety of Existing Reactors
  • Instrumentation, Measurement Techniques and Testing
  • Advanced Reactors Thermalhydraulics (Gen III+, IV, INPRO, Fusion)
  • Waste Management Thermalhydraulics
  • Thermalhydraulics of Non-electricity Generating Nuclear Equipment
  • Special Topics (Organized Sessions) include: 
  • Session on Thermal Hydraulics and Structural Integrity in Connection to Aging and Life Extension;
  • Session on BEPU (Best Estimate code Plus Uncertainty) method, CSAU, Statistical Methods; Session on the Study of Pressurized Thermal Shock;
  • OECD session on Thermal Hydraulic Benchmarks;
  • OECD/NEA session on Analysis and Management of Accidents (BEMUSE, CFD Studies); IAEA session on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Monju Reactor Vessel;
  • Westinghouse session on Full Spectrum LOCA A Realistic LOCA Evaluation Model Applicable to the Full Range of Break Sizes using WCOBRA/TRAC-TF2 code.

 

The proceedings include the papers and presentations given at the 5th CNS International Steam Generator Conference.if you need a single paper please contact us.

 

 

Preconference Workshop: BEPU (Best Estimate Code Plus Uncertainty) Methodology

 

 

Room: Tom Thomson
Session Chair:

·         Alessandro Petruzzi (GRNSPG, Università di Pisa)

 

Preconference Workshop: OECD/NRC Benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT) - Third Workshop

 

 

Room: Varley
Session Chairs:

·         Maria Avramova (The Pennsylvania State University)

·         David Novog (McMaster University)

·         Alexander Velazquez-Lozada (U.S. Nuclear Regulatory Commission)

 

CASL Program Meeting

 

 

Room: Casson
Session Chair:

·         Paul Turinsky (Consortium for Advanced Simulation of LWRs)

 

IAEA Coordinated Research Project on Sodium Natural Circulation Tests Performed during PHENIX End-of-Life Experiments

 

 

Room: Richmond
Session Chairs:

·         David Pialla (CEA)

·         Stefano Monti (IAEA)

 

Paper: 636

Development of Interfacial Area Transport Equation, Modeling and Experimental Benchmark

 

·         Mamoru Ishii (Purdue University)

 

 

Paper: 632

Status and Perspective for a Multiscale Approach to Light Water Reactor Thermalhydraulic Simulation

 

·         Dominique Bestion (Commissariat à l’Énergie Atomique)

 

 

A1-1 Boiling and Condensation Fundamentals

 

 

Room: Toronto II
Session Chair:

·         Henryk Anglart (Royal Institute of Technology)

Session Co-Chair:

·         Ezra Elias (Israel Institute of Technology)

 

Paper: 13

Separate Effects of Surface Roughness, Wettability and Porosity on the Leidenfrost Temperature of Water

 

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

 

 

Paper: 39

Evaporation Heat Transfer of Hot Water from Horizontal Free Surface

 

·         Yasuo Koizumi (Shinshu University)

·         Yutaka Ebihara (Shinshu University)

·         Tatsuya Hirota (Shinshu University)

·         Michio Murase (Institute of Nuclear Safety System, Inc.)

 

 

Paper: 61

Experiments on Evaporating Pipe Flow

 

·         Dirk Lucas (HZDR)

·         Matthias Beyer (HZDR)

·         Lutz Szalinski (HZDR)

 

 

Paper: 68

Two-Phase Flow and Cross-Mixing Measurements in a Rod Bundle

 

·         Arto Ylönen (Paul Scherrer Institut)

·         Horst-Michael Prasser (ETH Zurich)

 

 

Paper: 98

Heat Transfer and Critical Heat Flux of Subcooled Water Flow Boiling in a Short Horizontal Tube

 

·         Koichi Hata (Institute of Advanced Energy, Kyoto University)

·         Naoto Kai (Kyoto University)

·         Yasuyuki Shirai (Kyoto University)

·         Suguru Masuzaki (National Institute for Fusion Science)

 

 

Paper: 55

Boiling Heat Transfer in Porous Media Composed of Particles

 

·         Bofeng Bai (Xi'an Jiaotong University)

·         Xiaojie Zhang (Xi'an Jiaotong University)

 

 

A12-1 Introductory Session on Non-Unity Prandtl Number Flows

 

 

Room: Tom Thomson
Session Chair:

·         Martin Rohde (Delft University of Technology)

Session Co-Chair:

·         Walter Ambrosini (Università di Pisa)

 

Paper: 574

Fluid Flow and Heat Transfer at Supercritical Pressure

 

·         J. D. Jackson (University of Manchester)

 

 

Paper: 485

Challenges in Simulation and Modeling of Heat Transfer in Low-Prandtl Number Fluids

 

·         Günther Grötzbach (Karlsruhe Institute for Technology)

 

 

Paper: 582

Review of Some Experimental Studies of Turbulent Mixed Convection Covering a Wide Range Prandtl Number

 

·         J.D. Jackson (University of Manchester)

 

 

Paper: 63

European Developments in Single Phase Turbulence for Innovative Reactors

 

·         Ferry Roelofs (NRG)

·         Martin Rohde (Delft University of Technology)

·         Ivan Otic (Karlsruhe Institute for Technology)

·         Guillaume Brillant (IRSN)

·         Iztok Tiselj (Jožef Stefan Institute)

·         Henryk Anglart (Royal Institute of Technology)

·         Bojan Niceno (Paul Scherrer Institut)

·         Laurent Bricteux (Université catholique de Louvain)

·         Diego Angeli (UniMoRe)

·         Walter Ambrosini (Università di Pisa)

·         Djamel Lakehal (MIT, ASCOMP Gmbh, Switzerland)

·         Emilio Baglietto (CD-adapco)

·         Yassin A. Hassan (Texas A&M University)

·         Xu Cheng (Shanghai Jiao Tong University)

 

 

B3-1 Core Thermalhydraulics and Subchannel Analysis

 

 

Room: Carmichael & Jackson
Session Chair:

·         J. Terry Rogers (Carleton University)

Session Co-Chair:

·         Jianquiang Shan (Xi’an Jiaotong University)

 

Paper: 24

GOTHIC Simulation of Single-Channel Fuel Heatup Following Loss of Forced Flows

 

·         Xi-Qing Chen (AMEC NSS)

·         Ab Tahir (AMEC NSS)

·         Y. Parlatan (Ontario Power Generation)

·         M. Kwee (Bruce Power)

 

 

Paper: 38

Study of Enhanced Entrance Pressure Losses in a Rod Bundle Experiment Employing Heavy Liquid Metal Coolant

 

·         Abdalla Batta (Karlsruhe Institute for Technology)

·         Andreas Class (Karlsruhe Institute for Technology)

 

 

Paper: 45

An Experimental Investigation of the Effect of Flow Obstacles on Single-Phase Heat Transfer

 

·         Aurelian Tanase (CNSC, University of Ottawa)

·         Dionysisus Groeneveld (University of Ottawa)

·         Hussam Zahlan (University of Ottawa)

 

 

Paper: 56

Sensitivity Study on a CFD Model for the Analysis of Moderator Fluid Flow and Heat Transfer Inside CANDU Calandria

 

·         G. H. Lee (Korea Institute of Nuclear Safety)

·         S. W. Woo (Korea Institute of Nuclear Safety)

 

 

Paper: 104

Elements of Validation for LWRs Thermalhydraulic Studies With FLICA-OVAP

 

·         Philippe Fillion (CEA Saclay)

·         Matteo Bucci (CEA Saclay)

·         Anne Charmeau (CEA Saclay)

 

 

Paper: 133

Secondary Flows in PWR Hot Legs, CFD Brings Some Light to Better Understand Hot Leg Flows

 

·         Serge Bellet (EDF - Septen)

·         Sofiane Benhamadouche (EDF R&D)

 

 

C1-1 Molten Core Natural Convection, Physico-Chemical Phenomena, and Direct Containment Heating by Dispersed Molten Fuel

 

 

Room: Harris
Session Chair:

·         Pavel Kudinov (Royal Institute of Technology)

Session Co-Chair:

·         Rendall Gauntt (Sandia National Laboratories)

 

Paper: 96

CFD Model of CANDU Calandria Vessel Retention During Severe Accidents

 

·         Fei Song (Atomic Energy of Canada Limited)

·         Boris Lekakh (Atomic Energy of Canada Limited)

·         Ken Hau (Atomic Energy of Canada Limited)

 

 

Paper: 169

Analysis on Thermal Load Response of the In-Vessel Retention During a Severe Accident

 

·         Jae Ryong Lee (Korea Atomic Energy Research Institute)

·         Rae Joon Park (Korea Atomic Energy Research Institute)

·         Seong Wan Hong (Korea Atomic Energy Research Institute)

 

 

Paper: 317

CHF Experiments Using a 2-D Curved Test Section With Additives for IVR-ERVC Strategy

 

·         Tae Il Kim (Korea Advanced Institute of Science and Technology)

 

 

Paper: 19

Experimental Study of Hydrogen Combustion During DCH Events in Two Different Scales

 

·         Leonhard Meyer (Karlsruhe Institute for Technology)

·         Giancarlo Albrecht (Karlsruhe Institute for Technology)

 

 

Paper: 59

Severe Accident Modeling and Offsite Dose Consequence Evaluations for Nuclear Power Plant Emergency Planning

 

·         Shao-Shuan Chen (National Tsing Hua University)

·         Tsung-Sheng Feng (National Tsing Hua University)

·         Kai-Chun Huang (National Tsing Hua University)

·         Jong-Rong Wang (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Chunkuan Shih (National Tsing Hua University)

·         Y.H. Cheng (Industrial Tech. Res. Inst., Hsinchu, Taiwan)

 

 

Paper: 406

Validation of the Condensation Model for Containment Thermalhydraulics

 

·         Srinivasa Rao (Atomic Energy Regulatory Board, India)

·         Teany Thomas (Indian Institute of Technology Bombay)

·         Kannan Iyer (Indian Institute of Technology Bombay)

·         S.K. Gupta (Atomic Energy Regulatory Board, India)

 

 

F5-1 Instrumentation Technique

 

 

Room: MacDonald
Session Chair:

·         Stephan Leyer (AREVA NP GmbH)

Session Co-Chair:

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

 

Paper: 16

A Novel Infrared-Based Experimental Technique to Detect Phase Dynamics on Boiling Surfaces

 

·         Hyungdae Kim (Kyung Hee University)

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

 

 

Paper: 31

Use of the Carbon Ceramic Experimental Test Apparatus to Validate the HTTF Design

 

·         Seth Cadell (Oregon State University)

·         Brian Woods (Oregon State University)

 

 

Paper: 102

Venturi Fouling and What Can Cause an Overestimate of the Flow Rate by One Percent

 

·         Peter Hedberg (Remote CAE AB, Sweden)

·         Hans Nilsson (Ringhals AB, Sweden)

 

 

Paper: 156

Theoretical Basis of Non-Intrusive Ultrasonic Cross Correlation Flow Measurement Technology

 

·         Alexander Gurevich (De Montfort University)

·         Ibrahim Abdalla (De Montfort University)

·         Armando Lopez (Advanced Measurement and Analysis Group Inc.)

 

 

Paper: 227

Contactless Flowrate Sensors for NA, PBBI and PB Flows

 

·         Dominique Buchenau (HZDR)

·         Gunter Gerbeth (Helmholtz-Zentrum Dresden-Rossendorf)

·         Janis Priede (Coventry University)

 

 

Paper: 262

Development of Subchannel Void Measurement Sensor and Multidimensional Two-Phase Flow Dynamics in Rod Bundle

 

·         Takahiro Arai (Central Research Institute of Electric Power Industry)

·         Masahiro Furuya (CRIEPI)

·         Taizo Kanai (Central Research Institute of Electric Power Industry)

·         Kenetsu Shirakawa (Central Research Institute of Electric Power Industry)

 

 

E4-1 NPP Transients and Accidents Analysis

 

 

Room: Varley
Session Chair:

·         Alex Viktorov (CNSC)

Session Co-Chair:

·         Yanhua Yang (Shanghai Jiao Tong University)

 

Paper: 14

Approach to Conservative Deterministic Safety Analysis for Design Basis Accidents Based on Regulatory Requirements

 

·         Noreddine Mesmous (CNSC)

·         Janusz Kowalski (CNSC)

 

 

Paper: 115

Analytical and Experimental Assessment of CANDU Fuel Sheath Integrity Under Post Dryout Conditions

 

·         Mohamed E. Shawkat (AMEC NSS Ltd.)

·         Hisham Hasanein (AMEC NSS)

·         Yuksel Parlatan (Ontario Power Generation)

·         Todd Daniels (Ontario Power Generation)

·         Mohamed Bayoumi (AMEC NSS Ltd.)

·         Hassan Albasha (Bruce Power)

 

 

Paper: 389

Kuosheng BWR/6 Containment Pressure and Temperature Responses After Recirculation Line Break Using GOTHIC Code

 

·         Ansheng Lin (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Jong-Rong Wang (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Yen-Shu Chen (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Ruey-Yng Yuann (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Chunkuan Shih (National Tsing Hua University)

 

 

Paper: 505

Cyber-Security in a Nuclear Power Plant Simulator

 

·         M. Giersch (GRNSPG/UNIPI)

·         N. Muellner (GRNSPG/UNIPI)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

 

 

Paper: 554

Experimental Investigation of Quench Phenomena and Two-Phase Flow Behavior for Hot Horizontal Tubes Well Above the Limiting Temperature for Solid–Liquid Contact

 

·         Kifah Takrouri (McMaster University)

·         John Luxat (McMaster University)

·         Mohamed Hamed (McMaster University)

 

 

O8-1 OECD Thermalhydraulics Benchmarks

 

 

Room: Lismer
Session Chair:

·         Maria Avramova (The Pennsylvania State University)

Session Co-Chair:

·         Yixing Sung (Westinghouse Electric Company)

 

Paper: 69

OECD/NRC PSBT Benchmark: CFD Analysis of Boiling Flow in PWR Subchannel Geometry Using ANSYS CFX

 

·         Johannes Weis (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Martina Scheuerer (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

 

 

Paper: 85

Investigation of the PWR Subchannel Void Distribution Benchmark (OECD/NRC PSBT Benchmark) Using ANSYS CFX

 

·         Thomas Frank (ANSYS Germany)

·         Florian Reiterer (ANSYS Germany)

·         Conxita Lifante (ANSYS Germany)

 

 

Paper: 127

OECD/NEA PSBT Benchmark: Simulation of the Steady-State Sub-Channel Test-Case with NEPTUNE CFD

 

·         Cyril Baudry (EDF)

·         Mathieu Guingo (EDF)

·         Alexandre Douce (EDF)

·         Jérôme Laviéville (EDF)

·         Stéphane Mimouni (EDF R&D)

·         Marc Boucker (EDF)

 

 

Paper: 149

CFD Analysis of a Void Distribution Benchmark of the NUPEC PSBT Tests

 

·         Eckhard Krepper (Helmholtz-Zentrum Dresden-Rossendorf)

·         Roland Rzehak (Forschungszentrum Dresden-Rossendorf)

 

 

Paper: 273

CFD Application to PWR Subchannel Void Distribution Benchmark

 

·         Wang-Kee In (Korea Atomic Energy Research Institute)

·         Chang-Hwan Shin (Korea Atomic Energy Research Institute)

·         Tae-Hyun Chun (Korea Atomic Energy Research Institute)

 

 

A1-2 Boiling and Condensation Fundamentals

 

 

Room: Toronto II
Session Chair:

·         Dirk Lucas (HZDR)

Session Co-Chair:

·         Yujun Guo (CNSC)

 

Paper: 112

Quantification of Uncertainties Associated With Using 28-Element BLA CHF Correlation

 

·         Hisham Hasanein (AMEC NSS)

·         Yuksel Parlatan (Ontario Power Generation)

·         Ab Tahir (AMEC NSS)

·         Jose Torres (Ontario Power Generation)

·         Michael Kisil (Ontario Power Generation)

·         Sun John (AMEC NSS)

 

 

Paper: 117

Void Fraction Evolution in Subcooled Flow Boiling Under Low-Pressure and Low-Flowrate Condition

 

·         Tomio Okawa (Osaka University)

·         Yosuke Yamagoe (Osaka University)

·         Rouhollah Ahmadi (Osaka University)

 

 

Paper: 134

Experimental and Computational Analysis of Steam Condensation in the Presence of Air and Helium

 

·         Matteo Bucci (CEA Saclay)

·         Walter Ambrosini (Università di Pisa)

·         Nicola Forgione (Università di Pisa)

·         Francesco Oriolo (University of Pisa)

·         Sandro Paci (University of Pisa)

 

 

Paper: 135

Experimental Investigation on Steam Condensation in the Presence of Air and Helium: Forced Convection Conditions

 

·         Matteo Bucci (CEA Saclay)

·         Walter Ambrosini (Università di Pisa)

·         Nicola Forgione (Università di Pisa)

·         Donato Lioce (Westinghouse Electric Belgium)

 

 

Paper: 177

Study on Temperature Fluctuation Phenomena in Pressurizer Spray Pipe of Pressurized Water Reactor

 

·         Hideki Tamura (Kobe University)

·         Yusuke Ozaki (Kobe University)

·         Nobuyuki Takenaka (Kobe University)

·         Koji Miyishi (Institute of Nuclear Safety System Inc.)

·         Akira Nakamura (Institute of Nuclear Safety System, Inc.)

 

 

Paper: 311

Bubble Dynamics in Single Component Fluid

 

·         Nikolay Kolev (Siemens AG)

 

 

A12-2 Thermalhydraulics of Low Prandtl-Number (Liquid Metal) Flows (I)

 

 

Room: Tom Thomson
Session Chair:

·         Ferry Roelofs (NRG)

Session Co-Chair:

·         Christophe Tjoen (Delft University of Technology)

 

Paper: 130

DNS and LES of Turbulent Channel Flows at Very Low Prandtl Number: Application to Convection in Lead-Bismuth

 

·         Laurent Bricteux (Université catholique de Louvain)

·         Matthieu Duponcheel (Université catholique de Louvain)

·         Grégoire Winckelmans (Université catholique de Louvain)

·         Yann Bartosiewicz (Université catholique de Louvain)

 

 

Paper: 282

Effect of Wall Boundary Condition on Scalar Transfer in Turbulent Low-Prandtl-Number Convection

 

·         Ivan Otic (Karlsruhe Institute for Technology)

·         Xu Cheng (Shanghai Jiao Tong University)

 

 

Paper: 364

DNS of Turbulent Channel Flow at Reτ=395, 590 and Pr=0.01

 

·         Iztok Tiselj (Jožef Stefan Institute)

 

 

Paper: 486

Modeling the Turbulent Heat Fluxes in Low Prandtl Number Shear Flows

 

·         Thomas Baumann (Karlsruhe Institute for Technology)

·         André Loges (Karlsruhe Institute for Technology)

·         Luca Marocco (Politecnico di Milano)

·         Torsten Schenkel (FAU Busan, Friedrich-Alexander-Universität Erlangen-Nürnberg)

·         Thomas Wetzel (Karlsruhe Institute for Technology)

·         Robert Stieglitz (Karlsruhe Institute for Technology)

 

 

Paper: 329

Scaling Analysis for the European Heavy Liquid Metal Scaled Pool Facility Escape

 

·         Katrien Van Tichelen (SCK•CEN)

·         Matthias Vanderhaegen (SCK•CEN)

·         Santhosh Jayarayu (NRG)

·         Steven Keijers (SCK•CEN)

·         Ferry Roelofs (NRG)

 

 

Paper: 439

Experimental Investigation on Turbulent Heat Transfer in Liquid Metal Along a Heated Rod in a Vertical Annulus

 

·         André Loges (Karlsruhe Institute for Technology)

·         Thomas Baumann (Karlsruhe Institute for Technology)

·         Luca Marocco (Politecnico di Milano)

·         Thomas Wetzel (Karlsruhe Institute for Technology)

·         Robert Stieglitz (Karlsruhe Institute for Technology)

 

 

B3-2 Core Thermalhydraulics and Subchannel Analysis

 

 

Room: Carmichael & Jackson
Session Chair:

·         Jianquiang Shan (Xi'an Jiaotong University, Shaanxi, China)

Session Co-Chair:

·         Jean-Marie Le Corre (Westinghouse Electric Sweden AB)

 

Paper: 229

VIPRE-W / MEFISTO-T, a Mechanistic Tool for Transient Prediction of Dryout in BWR Fuel Assemblies

 

·         Carl Adamsson (Westinghouse Electric Sweden AB)

·         Jean-Marie Le Corre (Westinghouse Electric Sweden AB)

 

 

Paper: 238

Analyses of Single-Phase Heat Transfer and Onset of Nucleate Boiling in a Rod Bundle With Mixing Vane Grids

 

·         Pierre Péturaud (Electricité de France)

·         Robert Salko (The Pennsylvania State University)

·         André Bergeron (Commissariat à l'Energie Atomique)

·         Suresh Yagnik (Electric Power Research Institute)

·         Maria Avramova (The Pennsylvania State University)

 

 

Paper: 387

Droplet Entrainment and Deposition Rate Models for Determination of Boiling Transition in BWR Fuel Assembly

 

·         Pradip Saha (GE Hitachi Nuclear Energy)

·         Belgacem Hizoum (GE Hitachi Nuclear Energy)

·         Jens G. Andersen (GE Hitachi Nuclear Energy)

·         Kristin Whitlow (GE Hitachi Nuclear Energy)

 

 

Paper: 395

On the Development of a Grid-Enhanced Single-Phase Convective Heat Transfer Correlation

 

·         Douglas Miller (The Pennsylvania State University)

·         Fan-Bill Cheung (The Pennsylvania State University)

·         Stephen M. Bajorek (U.S. Nuclear Regulatory Commission)

 

 

Paper: 420

Heat Flux and Temperature Determination on the Control Rod Outer Surface

 

·         Jan Taler (Cracow University of Technology)

·         Artur Cebula (Cracow University of Technology)

·         Jerzy Marcinkiewicz (Forsmarks Kraftgrupp AB)

·         Hernan Tinoco (Forsmarks Kraftgrupp AB)

 

 

Paper: 434

Developement of the New Basic Correlation "MG-S" for CHF Prediction of the PWR Fuels

 

·         Tadakatsu Yodo (Mitsubishi Heavy Industries, LTD.)

·         Yusuke Sato (Mitsubishi Heavy Industries, LTD.)

·         Takanori Yumura (Mitsubishi Heavy Industries, LTD.)

·         Yasushi Makino (Mitsubishi Heavy Industries, LTD.)

·         Takayuki Suemura (Mitsubishi Heavy Industries, LTD.)

 

 

C2-1 Natural Convection and Mixing phenomena, Modeling and Experiments

 

 

Room: Harris
Session Chair:

·         Domenico Paladino (Paul Scherrer Institut)

Session Co-Chair:

·         Tetsuaki Takeda (University of Yamanashi)

 

Paper: 183

Particle Precipitation and Mixing Simulated by Rigid Dynamic-Moving Particle Semi-Implicit (RD-MPS) Method

 

·         Shane Park (KEPCO Nuclear Fuel)

·         Hyun Sun Park (SINEWSTEK)

·         Gyoodong Jeun (Hanyang University)

·         Beom Jin Cho (KEPCO Nuclear Fuel)

 

 

Paper: 208

CFD Simulation of Hydrogen Mixing and Mitigation by Means of Passive Auto-Catalytic Recombiners

 

·         Stephan Kelm (Forschungszentrum Juelich GmbH)

·         Ernst-Arndt Reinecke (Forschungszentrum Juelich GmbH)

·         Wilfried Jahn (Forschungszentrum Juelich GmbH)

·         Hans-Josef Allelein (RWTH Aachen University)

 

 

Paper: 609

Containment Cooler Performance in the Presence of Light Non Condensable Gas with Cooler Location as a Primary Parameter

 

·         Guillaume Mignot (Paul Scherrer Institut)

·         Ralf Kapulla (Paul Scherrer Institut)

·         Nejdet Erkan (Paul Scherrer Institut)

·         Robert Zboray (Paul Scherrer Institut)

·         Domenico Paladino (Paul Scherrer Institut)

 

 

Paper: 621

Stereo Particle-Image-Velocimetry Measurements of an Unstable Air Stratification Due to Natural Convection in a Model Containment

 

·         Marco Gärtner (TU Darmstadt)

·         Cameron Tropea (TU Darmstadt)

·         Suad Jakirlic (TU Darmstadt)

·         Sanjeev Gupta (Becker Technologies GmbH)

 

 

F5-2 Instrumentation Technique

 

 

Room: MacDonald
Session Chair:

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

Session Co-Chair:

·         Stephan Leyer (AREVA NP GmbH)

 

Paper: 532

Ultra Fast Electron Beam X-Ray CT for Two Phase Flow Phenomena

 

·         Frank Barthel (Forschungszentrum Dresden-Rossendorf e.V.)

·         Dietrich Hoppe (HZDR)

·         Lutz Szalinski (HZDR)

·         Matthias Beyer (HZDR)

·         Uwe Hampel (Forschungszentrum Dresden-Rossendorf e.V., Dresden, Germany)

 

 

Paper: 281

Investigating Annular Flows and the Effect of Functional Spacers in an Adiabatic Double-Subchannel Model of a BWR Fuel Bundle by Ultra-Fast X-Ray Tomography

 

·         Robert Zboray (Paul Scherrer Institut)

·         Marc Guetg (Swiss Federal Institute of Technology, ETH Zurich)

·         John Kickhofel (Swiss Federal Institute of Technology, ETH Zurich)

·         Frank Barthel (Forschungszentrum Dresden-Rossendorf e.V.)

·         Uwe Sprewitz (Forschungszentrum Dresden-Rossendorf e.V.)

·         Uwe Hampel (Forschungszentrum Dresden-Rossendorf e.V., Dresden, Germany)

·         Horst-Michael Prasser (ETH Zurich)

 

 

Paper: 396

Determining Temperature and Stress Distributions in Pressure Components Based on Measurements of Internal Pressure and Temperature at the Outer Easily Accessible Surface

 

·         Jan Taler (Cracow University of Technology)

·         Bohdan Weglowski (Cracow University of Technology)

·         Tomasz Sobota (Cracow University of Technology)

·         Magdalena Jaremkiewicz (Cracow University of Technology)

·         Dawid Taler (University of Science and Technology AGH)

 

 

Paper: 487

Liquid Film Thickness of Individual Bubbles in a Narrow Channel

 

·         Daisuke Ito (ETH Zurich)

·         Horst-Michael Prasser (ETH Zurich)

·         Masanori Aritomi (Tokyo Institute of Technology)

 

 

Paper: 489

Heat Transfer in a Non Adiabatic Calorimeter: Numerical Parametric Study Without and With Nuclear Heating Deposit

 

·         Ossama Merroun (Université de Provence LCP)

·         Christelle Raynaud (Electricité de France)

·         Julie Brun (Université de Provence LCP)

·         Michel Carette (Université de Provence LCP)

·         Aurika Janulyte (Université de Provence LCP)

·         Yves Zerega (Université de Provence LCP)

·         Jacques Andre (Université de Provence LCP)

·         Abdallah Lyoussi (CEA)

·         Gilles Bignan (CEA)

·         Jean-Pierre Chauvin (CEA)

·         Damien Fourmentel (CEA)

·         Christian Gonnier (CEA)

·         Philippe Guimbal (CEA)

·         Jean-Yves Malo (CEA)

·         Jean-François Villard (CEA)

 

 

Paper: 615

Experimental Droplet Deposition Distribution Downstream of Functional Spacers in an Adiabatic BWR Mock-Up Model

 

·         Manuel Damsohn (ETH Zurich)

·         Horst-Michael Prasser (ETH Zurich)

 

 

E4-2 NPP Transients and Accidents Analysis

 

 

Room: Varley
Session Chair:

·         Chunkuan Shih (National Tsing Hua University)

Session Co-Chair:

·         Yanhua Yang (Shanghai Jiao Tong University)

 

Paper: 113

Pragmatic Application of the Precautionary Principle to Deal with Unknown Safety Challenges

 

·         Gerry Frappier (CNSC)

·         Alex Viktorov (CNSC)

 

 

Paper: 627

A Computational Study on Instrumentation Guide Tube Failure During a Severe Accident in Boiling Water Reactors

 

·         Walter Villanueva (Royal Institute of Technology)

·         Chi-Thanh Tran (Royal Institute of Technology)

·         Pavel Kudinov (Royal Institute of Technology)

 

 

Paper: 628

Assessment with Coupled Thermo-Mechanical Creep Analysis of Combined CRGT and External Vessel Cooling Efficiency for a BWR

 

·         Walter Villanueva (Royal Institute of Technology)

·         Chi-Thanh Tran (Royal Institute of Technology)

·         Pavel Kudinov (Royal Institute of Technology)

 

 

Paper: 221

Chemical Effects and the Impact to Insulation Debris Filtercakes at ECCS Upstream and Downstram Components

 

·         Sören Alt ((University of Applied Sciences Zittau//Goerlitz))

·         Miriam Hoelker (University of Applied Sciences Zittau/Goerlitz, Germany)

·         Wolfgang Kaestner (University of Applied Sciences Zittau/Goerlitz, Germany)

·         Andrè Seeliger (University of Applied Sciences Zittau/Goerlitz, Germany)

·         Stefan Renger (Hochschule Zittau/Goerlitz)

·         Wolfgang Hoffmann (Forschungszentrum Dresden-Rossendorf, Germany)

·         Holger Kryk (Helmholtz-Zentrum Dresden-Rossendorf)

 

 

O8-2 OECD Thermalhydraulics Benchmarks

 

 

Room: Lismer
Session Chair:

·         Alexander Velazquez-Lozada (U.S. Nuclear Regulatory Commission)

Session Co-Chair:

·         Maria Avramova (The Pennsylvania State University)

 

Paper: 103

Analysis of the NUPEC PSBT Tests with FLICA-OVAP. Part 1: Void Distribution Benchmark

 

·         Philippe Fillion (CEA Saclay)

·         Matteo Bucci (CEA Saclay)

 

 

Paper: 151

Comparative Analysis of CTF and Trace Thermalhydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database

 

·         Maria Avramova (The Pennsylvania State University)

·         Alexander Velazquez-Lozada (U.S. Nuclear Regulatory Commission)

·         Adam Rubin (The Pennsylvania State University)

 

 

Paper: 332

Prediction of Void Fraction in a Subchannel and Bundle Geometry with FLICA4 and TRACE

 

·         Tae-Wan Kim (Paul Scherrer Institut)

·         Annalisa Manera (Paul Scherrer Institut)

 

 

Paper: 388

VIPRE-W Benchmark With PSBT Void and Temperature Test Data

 

·         Yixing Sung (Westinghouse Electric Company)

·         Robert Oelrich (Westinghouse Electric Company)

·         Charles Lee (Westinghouse Electric Company)

·         Nicolas Ruiz-Esquide (INVAP, Argentina)

·         Marcelo Gambetta (INVAP, Argentina)

·         Claudio Mazufri (INVAP, Argentina)

 

 

Paper: 415

Void Fraction Prediction of NUPEC PSBT Tests by CATHARE Code

 

·         Alessandro Del Nevo (GRNSPG, Università di Pisa)

·         Lorenzo Michelotti (UNIPI)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

·         F. Moretti (UNIPI)

·         D. Rozzia (UNIPI)

 

 

Panel Session: Global Cooperation in Nuclear Engineering Education

 

 

Room: Toronto II
Session Chair:

·         Jong Kim (KAIST)

 

 

Monday Panelists: Michael Podowski (Rensselaer Polytechnic Institute), Hisashi Ninokata (Tokyo Institute of Technology), Phil Beeley (Khalifa University United Arab Emirates), Xu Cheng (Shanghai Jiaotong University), Igor Pioro (University of Ontario Institute of Technology)

 

 

 

Panel Session - Lessons Learned from the Fukushima Accident

 

 

Room: Toronto II

 

 

Tuesday Panelists - Hisashi Ninokata (Japan), John Luxat (Canada), Michael Corradini (USA), Randall Gauntt (USA), Gerri Frappier (CNSC), Raj Sehgal (Europe)

 

 

 

Keynote Lectures Tuesday 1

 

 

Session Chair:

·         Raj Schgal (Royal Institute of Technology)

Session Co-Chair:

·         Hideki Kamide (Japan Atomic Energy Agency)

 

Paper: 640

Keynote - Thermalhydraulics of Sodium-Cooled Fast Reactors - Key Issues and Highlights

 

·         Hisashi Ninokata (Tokyo Institute of Technology)

·         Hideki Kamide (Japan Atomic Energy Agency)

 

 

Paper: 633

Korean Development of Advanced Thermalhydraulic Codes for Water Reactors and HTGRs: SPACE and GAMMA

 

·         Hee Cheon No (KAIST)

 

 

Keynote Lectures Tuesday 2

 

 

Session Chair:

·         Jean-Marc Delhaye (Clemson University)

Session Co-Chair:

·         Laurence Leung (Atomic Energy of Canada Limited)

 

Paper: 634

Supercritical Flow and Heat Transfer in Advanced Reactors

 

·         Michael Corradini (University of Wisconsin)

 

 

Paper: 635

Thermalhydraulics and Safety Concepts of Supercritical Water Cooled Reactors

 

·         Thomas Schulenberg (Karlsruhe Institute for Technology)

·         D.C. Visser (Nuclear Research and Consultancy Group, Petten)

 

 

Keynote Lectures Tuesday 3

 

 

Session Chair:

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

Session Co-Chair:

·         John Luxat (McMaster University)

 

Paper: 637

Experimental and Theoretical Tools to Support the Development of High-Performance LWR Fuel Elements

 

·         Horst-Michael Prasser (ETH Zurich)

 

 

Paper: Keynote

Some Challenges in Water-Cooled Reactor Thermalhydraulics

 

 

 

I1-1 Thermalhydraulics of Non Electricity Generating Nuclear Equipment

 

 

Room: Toronto II
Session Chair:

·         Yuichi Niibori (Tohoku University)

Session Co-Chair:

·         Janusz Kowalski (CNSC)

 

Paper: 25

Thermalhydraulic Analysis of Spent Fuel Baskets

 

·         Jake Xu (Atomic Energy of Canada Limited)

·         Khairy Khair (Atomic Energy of Canada Limited)

·         Ralph Granz (Atomic Energy of Canada Limited)

·         Amarjit Banwatt (Atomic Energy of Canada Limited)

 

 

Paper: 65

Design of a Decay Tank for a Pool Type Research Reactor with a CFD Model

 

·         Kyoungwoo Seo (Korea Atomic Energy Research Institute)

·         Young-Chul Park (Korea Atomic Energy Research Institute)

·         Daeyoung Chi (Korea Atomic Energy Research Institute)

·         Juhyeon Yoon (Korea Atomic Energy Research Institute)

 

 

Paper: 80

Thermal-Hydraulic Analysis of Water-Water Heat Exchanger Under Low Flow Conditions Using CFD Code

 

·         Masahito Takano (Research Institute of Nuclear Engineering, University of Fukui, Japan)

·         Hiroyasu Mochizuki (Research Institute of Nuclear Engineering, University of Fukui, Japan)

 

 

Paper: 224

Thermalhydraulic Analysis of the Multipurpose Research Reactor RMB Using a RELAP5 Model

 

·         Humberto Vitor Soares (UFMG)

·         Ivan Dionysio Aronne (CDTN/CNEN)

·         Ygor Henrique De Almeida (CDTN/CNEN)

·         Claubia Pereira (UFMG)

·         Antonella Lombardi Costa (UFMG)

·         Maria Auxiliadora Fortini Veloso (UFMG)

 

 

Paper: 556

Sticking of the AL-CAN Containing Irradiated TeO2 Target to the Bottom of the Dry Irradiation Channel of the 3MW TRIGA MK-II Research Reactor of Bangladesh Atomic Energy Commission

 

·         Md. Shafiqul Islam (Director)

 

 

A12-3 Thermalhydraulics of Low Prandtl-Number (Liquid Metal) Flows (II)

 

 

Room: Tom Thomson
Session Chair:

·         Walter Ambrosini (Università di Pisa)

Session Co-Chair:

·         Christophe Tjoen (Delft University of Technology)

 

Paper: 631

Thermally Stratified Sodium Channel Flow: Turbulence and Modelization

 

·         Marco Pellegrini (Tokyo Institute of Technology)

·         Hiroshi Endo (Japan Nuclear Energy Safety Organization)

·         Hisashi Ninokata (Tokyo Institute of Technology)

 

 

Paper: 182

Local Heat Transfer from the Corium Melt Pool to the Boiling Water Reactor Pressure Vessel Wall

 

·         Chi Thanh Tran (Institute of Energy, Hanoi, Vietnam)

·         Pavel Kudinov (Royal Institute of Technology)

 

 

Paper: 457

CFD Analysis of Heat Transfer in Low Prandtl Number Fluid Flows

 

·         A. Borgohain (Bhabha Atomic Research Centre)

·         N. K. Maheshwari (Bhabha Atomic Research Centre)

·         P. K. Vijayan (Bhabha Atomic Research Centre)

·         R. K. Sinha (Bhabha Atomic Research Centre)

 

 

Paper: 446

An Approach to Validation of Coupled CFD and System Thermalhydraulics Codes

 

·         Marti Jeltsov (Royal Institute of Technology)

·         Francesco Cadinu (Royal Institute of Technology)

·         Walter Villanueva (Royal Institute of Technology)

·         Aram Karbojian (Royal Institute of Technology)

·         Kaspar Kööp (Royal Institute of Technology)

·         Pavel Kudinov (Royal Institute of Technology)

 

 

Paper: 143

Investigation of the Influence of Turbulent Models on the Prediction of Heat Transfer to Low Prandtl Number Fluids

 

·         Roman Thiele (Royal Institute of Technology)

·         Weimin Ma (Royal Institute of Technology)

·         Henryk Anglart (Royal Institute of Technology)

 

 

B3-3 Core Thermalhydraulics and Subchannel Analysis

 

 

Room: Carmichael & Jackson
Session Chair:

·         Jean-Marie Le Corre (Westinghouse Electric Sweden AB)

Session Co-Chair:

·         Donna Guillen (Idaho National Laboratory)

 

Paper: 478

Modelling and Validation of Turbulent Boiling Flow in a Rectangular Channel

 

·         Boštjan Končar (Jožef Stefan Institute)

·         Marko Matkovič (Jožef Stefan Institute)

 

 

Paper: 534

CFD Analysis of the 37-Element Fuel Channel for CANDU6 Reactor

 

·         Hyoung Tae Kim (Korea Atomic Energy Research Institute)

·         Bo Wook Rhee (Korea Atomic Energy Research Institute)

·         Joo Hwan Park (Korea Atomic Energy Research Institute)

 

 

Paper: 558

Developement of CHF Correlation "MG-NV" for Low Pressure and Low Velocity Conditions Applied to PWR Safety Analysis

 

·         Takanori Yumura (Mitsubishi Heavy Industries, LTD.)

·         Tadakatsu Yodo (Mitsubishi Heavy Industries, LTD.)

·         Yasushi Makino (Mitsubishi Heavy Industries, LTD.)

·         Takayuki Suemura (Mitsubishi Heavy Industries, LTD.)

 

 

Paper: 571

Assessment of CHF Characteristics at Subcooled Conditions for the CANDU CANFLEX Bundle

 

·         Nihan Onder (Atomic Energy of Canada Limited)

·         Laurence Leung (Atomic Energy of Canada Limited)

 

 

Paper: 579

Validation of Subchannel Code Kamui: Analysis of Outlet Temperature Profiles of a 19-Pin Test Assembly

 

·         Syeilendra Pramuditya (Tokyo Institute of Technology)

·         Hisashi Ninokata (Tokyo Institute of Technology)

 

 

Paper: 581

Determination of Mixing Factors for VVER-440 Fuel Assembly Head

 

·         Sándor Tóth (Institute of Nuclear Techniques, Budapest University of Technology and Economics)

·         Attila Aszódi (Institute of Nuclear Techniques, Budapest University of Technology and Economics)

 

 

C6-1 Debris Bed Cooling

 

 

Room: Harris
Session Chair:

·         Alexei Miassoedov (Karlsruhe Institute for Technology)

Session Co-Chair:

·         Domenico Paladino (Paul Scherrer Institut)

 

Paper: 26

Live L4 and Live L5L Experiments on Melt Pool and Crust Behaviour in the RPV Lower Head

 

·         Xiaoyang Gaus-Liu

·         Alexei Miassoedov (Karlsruhe Institute for Technology)

·         Jerzy Foit

·         Thomas Cron

·         Frank Kretzschmar

·         Thomas Wenz

·         Silke Schmidt-Stiefel (Karlsruhe Institute for Technology)

 

 

Paper: 126

Experimental Program on Debris Reflooding (PEARL) - Results on Prelude Facility

 

·         Repetto Georges (Institut de Radioprotection et de Sûreté Nucléaire)

·         Garcin Thierry (Institut de Radioprotection et de Sûreté Nucléaire)

·         Eymery Stéphane (Institut de Radioprotection et de Sûreté Nucléaire)

·         March Philippe (Institut de Radioprotection et de Sûreté Nucléaire)

·         Florian Fichot (Institut de Radioprotection et de Sûreté Nucléaire)

 

 

Paper: 128

Quench Front Progression in a Superheated Porous Medium: Experimental Analysis and Model Development

 

·         Andrea Bachrata (IRSN)

·         Florian Fichot (IRSN)

·         Georges Repetto (IRSN)

·         Michel Quintard (IMFT)

·         Joelle Fleurot (IRSN)

 

 

Paper: 136

An Experimental Study on Two-Phase Flow and Coolability of Particulate Beds Packed with Multi-Size Particles

 

·         Liangxing Li (Royal Institute of Technology)

·         Sachin Thakre (Royal Institute of Technology)

·         Weimin Ma (Royal Institute of Technology)

 

 

Paper: 161

Coolability of a DEBRIS Bed: Quenching Experiments

 

·         Muhammad Rashid (Institute of Nuclear Technology and Energy Systems, Universität Stuttgart)

·         Rudi Kulenovic (Institute of Nuclear Technology and Energy Systems, Universität Stuttgart)

·         Eckart Laurien (Institute for Nuclear Technology and Energy Systems (IKE))

·         Saidur Rahman (Institute of Nuclear Technology and Energy Systems, Universität Stuttgart)

·         Manfred Bürger (Institute of Nuclear Technology and Energy Systems, Universität Stuttgart)

 

 

Paper: 543

Prediction of Mass Fraction of Agglomerated Debris in a LWR Severe Accident

 

·         Pavel Kudinov (Royal Institute of Technology)

·         Mikhail Davydov (Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety (EREC))

 

 

D9-1 CASL – Thermalhydraulics Activities in the Consortium for Advanced Simulation of LWRs

 

 

Room: MacDonald
Session Chair:

·         Robert Lowrie (Los Alamos National Laboratory)

Session Co-Chair:

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

 

Paper: 121

DNS for Multiphase Flow Model Generation and Validation

 

·         Gretar Tryggvason (University of Notre Dame)

·         Jiacai Lu (Worcester Polytechnic Institute)

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

 

 

Paper: 254

Coupled Computational Fluid Dynamics and MOC Neutronic Simulations of Westinghouse PWR Fuel Assemblies With Grid Spacers

 

·         Jin Yan (Westinghouse Electric Company)

·         Brendan Kochunas (University of Michigan)

·         Mathieu Hursin (University of Michigan)

·         Thomas Downar (University of Michigan)

·         Andrew Godfrey (Oak Ridge National Laboratory)

·         Zeses Karoutas (Westinghouse Electric Company)

·         Emilio Baglietto (CD-adapco)

 

 

Paper: 266

On the Development of Parallel Linear Solvers for Simulations of Reactor Thermalhydraulics

 

·         Yan Yan (Columbia University)

·         Steven Antal (RPI)

·         Brian Edge (RPI)

·         David Keyes (Columbia University)

·         Dillon Shaver (RPI)

·         Igor Bolotnov (RPI)

·         Michael Podowski (RPI)

 

 

Paper: 338

Advanced Thermalhydraulic Method Using 3X3 Pin Modeling

 

·         Zeses Karoutas (Westinghouse Electric Company)

·         Jin Yan (Westinghouse Electric Company)

·         Michael Conner (Westinghouse Electric Company)

·         Abdel Mandour (Westinghouse Electric Company)

 

 

Paper: 500

Reactor Core Sub-Assembly Simulations Using a Stabilized Finite Element Method

 

·         Thomas Smith (Sandia National Laboratories)

·         John Shadid (Sandia National Laboratories)

·         Roger Pawlowski (Sandia National Laboratories)

·         Eric Cyr (Sandia National Laboratories)

 

 

G4-1 - Gas Cooled Fast Reactors and Very High Temperature Reactors; CFD Calculations

 

 

Room: Varley
Session Chair:

·         Jan-Patrice Simoneau (AREVA)

Session Co-Chair:

·         Tetsuaki Takeda (University of Yamanashi)

 

Paper: 58

Effect of Non-Uniform Porosity Distribution on Thermalhydraulics in a Pebble Bed Reactor

 

·         Gert Jan Auwerda (Delft University of Technology)

·         Yanhua Zheng (Tsinghua University)

·         Danny Lathouwers (Delft University of Technology)

·         Jan-Leen Kloosterman (Delft University of Technology)

 

 

Paper: 141

Calibration of a Pebble Bed Configuration for Direct Numerical Simulation

 

·         A. Shams (Nuclear Research and Consultancy Group, Petten)

·         F. Roelofs (Nuclear Research and Consultancy Group, Petten)

·         E.M.J Komen (Nuclear Research and Consultancy Group, Petten)

·         Emilio Baglietto (CD-adapco)

 

 

Paper: 167

CFD Aided Design of the Experimental Helium Loop for VHTR Simulation

 

·         Churl Yoon (Korea Atomic Energy Research Institute)

·         Sung Deok Hong (Korea Atomic Energy Research Institute)

·         Jae Man Noh (Korea Atomic Energy Research Institute)

·         Yong Wan Kim (Korea Atomic Energy Research Institute)

·         Jong Hwa Chang (Korea Atomic Energy Research Institute)

 

 

Paper: 283

Validation and Application of 3D-Methods for the Design and Safety Analysis of High Temperature Reactors

 

·         Johannes Bader (University of Stuttgart)

·         Janis Lapins (University of Stuttgart)

·         Michael Buck (University of Stuttgart)

·         Wolfgang Bernnat (University of Stuttgart)

·         Eckart Laurien (Institute for Nuclear Technology and Energy Systems (IKE))

 

 

Paper: 383

Isothermal Air Ingress Validation Experiments

 

·         Chang Oh (Idaho National Laboratory)

·         Eung Kim (Idaho National Laboratory)

 

 

O8-3 OECD Thermalhydraulics Benchmarks

 

 

Room: Lismer
Session Chair:

·         Maria Avramova (The Pennsylvania State University)

Session Co-Chair:

·         Alexander Velazquez-Lozada (U.S. Nuclear Regulatory Commission)

 

Paper: 105

Analisys of the NUPEC PSBT Tests With FLICA-OVAP Part 2: DNB Benchmark

 

·         Matteo Bucci (CEA Saclay)

·         Philippe Fillion (CEA Saclay)

 

 

Paper: 153

Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmarks Database

 

·         Maria Avramova (The Pennsylvania State University)

·         Diana Cuervo (Technical University of Madrid)

 

 

Paper: 191

Validation of PWR-Relevant Models of Subchanflow Using the NUPEC PSBT Data

 

·         Ana Berkhan (Karlsruhe Institute for Technology)

·         Victor Sánchez Espinoza (Karlsruhe Institute for Technology)

·         Uwe Imke (Karlsruhe Institute for Technology)

 

 

Paper: 403

Analysis of PSBT Benchmark Exercises for Void Distribution and DNB Using a Subchannel Code MATRA

 

·         Dae-Hyun Hwang (Korea Atomic Energy Research Institute)

·         Seong Jin Kim (Korea Atomic Energy Research Institute)

·         Kyong-Won Seo (Korea Atomic Energy Research Institute)

 

 

Paper: 607

Subchannel and Rod Bundle PSBT Simulation With CATHARE-3

 

·         Michel Valette (CEA)

 

 

A1-3 Boiling and Condensation Fundamentals

 

 

Room: Toronto II
Session Chair:

·         Tomio Okawa (Osaka University)

Session Co-Chair:

·         Ezra Elias (Israel Institute of Technology)

 

Paper: 459

Measurement of Subcooled Boiling Pressure Drop and Local Heat Transfer Coefficient in Horizontal Channels Under LPLF Conditions

 

·         P.K. Baburajan (Atomic Energy Regulatory Board, India)

·         S.K. Gupta (Atomic Energy Regulatory Board, India)

·         Govind Singh Bisht (Indian Institute of Technology Bombay)

·         S.V. Prabhu (Indian Institute of Technology Bombay)

 

 

Paper: 618

Onset of Stable Dryout Condition in Diabatic Annular Two-Phase Flow

 

·         Henryk Anglart (Royal Institute of Technology)

 

 

Paper: 620

Subcooled Boiling Critical Heat Flux of Water in Lower Flow Upward in Tubes for Pressure up to 22 MPa

 

·         Yuzhou Chen (China Institute of Atomic Energy)

·         Chunsheng Yang (China Institute of Atomic Energy)

·         Minfu Zhao (China Institute of Atomic Energy)

·         Keming Bi (China Institute of Atomic Energy)

·         Kaiwen Du (China Institute of Atomic Energy)

·         Shuming Zhang (China Institute of Atomic Energy)

 

 

Paper: 469

A Model for Droplet Entrainment Rate in Horizontal Stratified Flow

 

·         François Henry (Université catholique de Louvain)

·         Yann Bartosiewicz (Université catholique de Louvain)

·         Valette Michel (CEA/DEN/DER/SSTH)

 

 

A12-4 Thermalhydraulics of High Prandtl-Number (Supercritical) Flows (I)

 

 

Room: Tom Thomson
Session Chair:

·         Martin Rohde (Delft University of Technology)

Session Co-Chair:

·         Ferry Roelofs (NRG)

 

Paper: 445

Influence of Numerical Tools on the Flow and Heat Transfer of Super-Critical Water

 

·         A. Shams (Nuclear Research and Consultancy Group, Petten)

·         D.C. Visser (Nuclear Research and Consultancy Group, Petten)

·         F. Roelofs (Nuclear Research and Consultancy Group, Petten)

 

 

Paper: 347

Numerical Simulation of Flow and Thermal Field in Supercritical Pressure Carbon Dioxide Flowing Upward in a Narrow Tube

 

·         Yoonyeong Bae (Korea Atomic Energy Research Institute)

·         Sung Deok Hong (Korea Atomic Energy Research Institute)

·         Yong Wan Kim (Korea Atomic Energy Research Institute)

 

 

Paper: 599

Progress in the Prediction of Non-Unity Prandtl Number Flows Using TransAT

 

·         Jarunan Panyasantisuk (ASCOMP GmbH)

·         Chidambaram Narayanan (ASCOMP GmbH)

·         Djamel Lakehal (MIT, ASCOMP Gmbh, Switzerland)

 

 

Paper: 601

An Algebraic Heat Flux Model in STAR-CCM+ for Application to Innovative Reactors

 

·         Emilio Baglietto (CD-adapco)

 

 

B3-4 Core Thermalhydraulics and Subchannel Analysis

 

 

Room: Carmichael & Jackson
Session Chair:

·         Donna Guillen (Idaho National Laboratory)

Session Co-Chair:

·         J. Terry Rogers (Carleton University)

 

Paper: 610

OECD International Standard Problem ISP-50 on the ATLAS DVI Line Break Test

 

·         Ki-Yong Choi (Korea Atomic Energy Research Institute)

·         Won-Pil Baek (Korea Atomic Energy Research Institute)

·         Hyun-Sik Park (Korea Atomic Energy Research Institute)

·         Seok Cho (Korea Atomic Energy Research Institute)

·         Kyoung-Ho Kang (Korea Atomic Energy Research Institute)

·         Yeon-Sik Kim (Korea Atomic Energy Research Institute)

 

 

Paper: 458

Multidimensional Boron Transport Modeling in Subchannel Approach

 

·         Ozkan Emre Ozdemir (The Pennsylvania State University)

·         Maria Avramova (The Pennsylvania State University)

·         Kenya Sato (Mitsubishi Heavy Industries, LTD.)

 

 

Paper: 499

Basis for Calculating Boron Dilution Scenarios in PWR by 3D Neutron Kinetics

 

·         Patricia Pla (GRNSPG-UNIPI/UPC)

·         Carlo Parisi (GRNSPG-UNIPI)

·         Regina Galetti (CNEN)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

·         Giorgio Galassi (GRNSPG-UNIPI)

·         Francesc Reventós (Universitat Politécnica de Catalunya)

 

 

Paper: 278

Thermalhydraulic Investigations of a Horizontal Rod Bundle Target at High-Powers During Operation

 

·         Rade Milenkovic (Paul Scherrer Institut)

·         Sergejs Dementjevs (Paul Scherrer Institut)

 

 

Paper: 382

Effect of Horizontal Flow on the Cooling of the Moderator Brick in the Advanced Gas-Cooled Reactor

 

·         Poo Balan Ganesan (University of Aberdeen)

·         Shuisheng He (University of Aberdeen)

·         Faik Hamad (University of Aberdeen)

·         Jim Gotts (EDF Energy, UK)

 

 

Paper: 638

RANS Modeling for Flow in Nuclear Fuel Bondle in Pressurized Water Reactors (PWR)

 

·         A. Gandhir (Texas A&M University)

·         Yassin A. Hassan (Texas A&M University)

 

 

C6-2 Experimental Debris Bed Cooling

 

 

Room: Harris
Session Chair:

·         Florian Fichot (Institut de Radioprotection et de Sûreté Nucléaire)

Session Co-Chair:

·         Domenico Paladino (Paul Scherrer Institut)

 

Paper: 199

Prediction of Dryout Heat Flux of Volumetrically Heated Particulate Bed Packed with Multi-Size Particles

 

·         Weimin Ma (Royal Institute of Technology)

 

 

Paper: 318

Sensitivity and Uncertainty Analysis of Debris Bed Coolability

 

·         Sergey Yakush (A. Yu. Ishlinskii Institute for Problems in Mechanics of the Russian Academy of Sciences)

·         Pavel Kudinov (Royal Institute of Technology)

·         Nazar Lubchenko (Moscow Institute of Physics and Technology)

 

 

Paper: 289

MCCI Simulation Comparison Between MELCOR and CORQUENCH

 

·         Kevin Robb (University of Wisconsin)

·         Michael Corradini (University of Wisconsin)

 

 

Paper: 290

Melt Eruption Modeling for MCCI Simulations

 

·         Kevin Robb (University of Wisconsin)

·         Michael Corradini (University of Wisconsin)

 

 

D9-2 CASL – Thermalhydraulics Activities in the Consortium for Advanced Simulation of LWRs

 

 

Room: MacDonald
Session Chair:

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

Session Co-Chair:

·         Robert Lowrie (Los Alamos National Laboratory)

 

Paper: 504

Parameter Sensitivity Study of Boiling and Two-Phase Flow Models in Computational Thermalhydraulics

 

·         Isaac Asher (University of Michigan)

·         Timothy Drzewiecki (University of Michigan)

·         Krzysztof Fidkowski (University of Michigan)

·         Thomas Downar (University of Michigan)

 

 

Paper: 360

Benchmarks for Interface-Tracking Codes in the Consortium for Advanced Simulation of LWRs (CASL)

 

·         Despoina Chatzikyriakou (Massachusetts Institute of Technology)

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

·         Djamel Lakehal (MIT, ASCOMP Gmbh, Switzerland)

 

 

Paper: 353

Subcooled Flow Boiling Experiment and Simulation for a Virtual Reactor

 

·         Masahiro Kawaji (City College of New York)

·         Randy Samaroo (City College of New York)

·         Joseph Kreynin (City College of New York)

·         Taehun Lee (City College of New York)

·         Sanjoy Banerjee (City College of New York)

 

 

Paper: 365

Flow Induced Vibration Forces on a Fuel Rod by LES CFD Analysis

 

·         A. Elmahdi (Westinghouse Electric Company)

·         R. Roger (Westinghouse Electric Company)

·         M. Conner (Westinghouse Electric Company)

·         Z. Karoutas (Westinghouse Electric Company)

·         Emilio Baglietto (CD-adapco)

 

 

G4-2 - Gas Cooled Fast Reactors and Very High Temperature Reactors; System Calculations

 

 

Room: Varley
Session Chair:

·         Richard Schultz (INEEL)

Session Co-Chair:

·         Jan-Patrice Simoneau (AREVA)

 

Paper: 37

Prevention and Investigations of Core Degradation in Case of Beyond Design Accidents of the 2400 MWTH Gas-Cooled Fast Reactor

 

·         Frederic Bertrand (CEA/DEN Cadarache)

·         Vincent Gatin (CEA/DEN Cadarache)

·         Fabrice Bentivoglio (CEA/DEN Grenoble)

·         Christine Gueneau (CEA/DEN Saclay)

 

 

Paper: 421

Coupled Nuclear-Thermalhydraulic Calculations for Fort St. Vrain Reactor

 

·         Benjamin Betzler (University of Michigan)

·         Eva Sunny (University of Michigan)

·         John Lee (University of Michigan)

·         William Martin (University of Michigan)

 

 

Paper: 490

Separate-Effects Experiments on the Hydrodynamics of Air Ingress Phenomena for the Very High Temperature Reactor

 

·         Seungjin Kim (The Pennsylvania State University)

·         Justin Talley (The Pennsylvania State University)

·         Mohan Yadav (The Pennsylvania State University)

·         Andrew Ireland (US Nuclear Regulatory Commission)

·         Stephen M. Bajorek (U.S. Nuclear Regulatory Commission)

 

 

Paper: 503

The US NRC Advanced Gas Reactor Evaluator (AGREE)

 

·         Timothy Drzewiecki (University of Michigan)

·         Volkan Seker (University of Michigan)

·         Joseph Kelly (US NRC)

·         Thomas Downar (University of Michigan)

 

 

Paper: 561

Transient Analysis of a Hydrogen-Desalination Cogeneration Nuclear Power Plant: Accident Scenarios within the Hydrogen Production Plant

 

·         Hyung Gon Jin (KAIST)

·         Hee Cheon No (KAIST)

·         Young Soo Kim (KAIST)

·         Ho Sik Kim (KAIST)

 

 

O8-4 OECD Thermalhydraulics Benchmarks

 

 

Room: Lismer
Session Chair:

·         Alexander Velazquez-Lozada (U.S. Nuclear Regulatory Commission)

Session Co-Chair:

·         Maria Avramova (The Pennsylvania State University)

 

Paper: 10

Validation of NEPTUNE CFD Two Phase Flow Models Using the OECD/NRC BFBT Benchmark Database

 

·         Jorge Pérez Mañes (Karlsruhe Institute for Technology)

·         Michael Böttcher (Karlsruhe Institute for Technology)

·         Victor Sánchez Espinoza (Karlsruhe Institute for Technology)

 

 

Paper: 107

Void Fraction Prediction by CATHARE 2 of OECD/NRC BFBT and PSBT Benchmarks

 

·         Luben Sabotinov (IRSN)

 

 

Paper: 214

Transient Void, Pressure Drop and Critical Power BFBT Benchmark Analysis and Results with VIPRE-W/MEFISTO-T

 

·         Jean-Marie Le Corre (Westinghouse Electric Sweden AB)

·         Carl Adamsson (Westinghouse Electric Sweden AB)

·         Pablo Avarez (Westinghouse)

 

 

Paper: 234

Benchmark of SIMULATE5 Thermalhydraulics Against the FRIGG and NUPEC Full Bundle Test Experiments

 

·         Gerardo Grandi (Studsvik Scandpower, Inc)

·         Sten-Örjan Lindahl (Studsvik Scandpower, Inc)

 

 

Panel Session: Issues and Future Directions of Thermalhydraulics R&Ds

 

 

Room: Toronto II

 

A2-1 Multifield Two-Phase Flow and Flow Regimes Identification and

 

 

Room: Toronto II
Session Chair:

·         Isao Kataoka (Osaka University)

Session Co-Chair:

·         Carl Adamsson (Westinghouse Electric Sweden AB)

 

Paper: 77

Properties of Flooding Wave in Vertical Churn Flow

 

·         Ke Wang (Xi'an Jiaotong University, Shaanxi, China)

·         Bofeng Bai (Xi'an Jiaotong University)

·         Bo Yang (Xi'an Jiaotong University, Shaanxi, China)

·         Chen Xie (Xi'an Jiaotong University, Shaanxi, China)

 

 

Paper: 89

Turbulence Modelling of High-Pressure Convective Boiling Two-Phase Flows

 

·         Jil Gueguen (CEA/Grenoble/Division for Nuclear Energy)

·         Fabrice Francois (CEA/Grenoble/Division for Nuclear Energy)

·         Hervé Lemonnier (CEA/Grenoble/Division for Nuclear Energy)

 

 

Paper: 251

Mal-Distribution Phenomena Induced by Multiple Solutions in Parallel Channels Heat Exchangers

 

·         Ezequiel Manavela Chiapero (Norwegian University of Science and Technology)

·         Maria Fernandino (Norwegian University of Science and Technology)

·         Carlos Alberto Dorao (Norwegian University of Science and Technology)

 

 

Paper: 309

Droplet Entrainment Rate in Vertical Annlar Two-Phase Flow

 

·         Pravin Sawant (Energy Research, Inc.)

·         Yang Liu (Purdue University)

·         Mamoru Ishii (Purdue University)

·         Mori Michitsugu (Meiji University)

 

 

Paper: 569

Dynamic Modeling Strategy for Flow Regime Transition in Gas-Liquid Two-Phase Flows

 

·         Xia Wang (The Ohio State University)

·         Xiaodong Sun (The Ohio State University)

·         Ben Doup (The Ohio State University)

·         Haihua Zhao (Idaho National Laboratory)

 

 

Paper: 617

Numerical Predictions of Bubbly Two-Phase Flows with Openfoam

 

·         Edouard Michta (KTH)

·         Kai Fu (KTH)

·         Henryk Anglart (Royal Institute of Technology)

·         Kristian Angele (Vattenfall R&D, Sweden)

 

 

A12-5 Thermalhydraulics of High Prandtl-Number (Supercritical) Flows (II)

 

 

Room: Tom Thomson
Session Chair:

·         Glenn Harvel (University of Ontario Institute of Technology)

Session Co-Chair:

·         Kannan Iyer (Indian Institute of Technology Bombay)

 

Paper: 451

Computational Study of Flow and Heat Transfer for Water Under Supercritical Conditions in a Vertical Pipe Using NAFA CFD Code

 

·         A. M. Vaidya (Bhabha Atomic Research Centre)

·         N. K. Maheshwari (Bhabha Atomic Research Centre)

·         P. K. Vijayan (Bhabha Atomic Research Centre)

·         D. Saha (Bhabha Atomic Research Centre)

 

 

Paper: 231

Sensitivity Analysis of Heated Wall Temperature and Velocity Distribution in CFD Simulations of the Upward Flow of Supercritical Water.

 

·         Maria Jaromin (Royal Institute of Technology)

·         Henryk Anglart (Royal Institute of Technology)

 

 

Paper: 488

Large Eddy Simulations of Turbulent Flows at Supercritical Pressure

 

·         Claus Kunik (Karlsruhe Institute for Technology)

·         Ivan Otic (Karlsruhe Institute for Technology)

·         Thomas Schulenberg (Karlsruhe Institute for Technology)

 

 

Paper: 559

Prediction of Wall Friction for Fluids at Supercritical Pressure with CFD Models

 

·         Morena Angelucci (Università di Pisa)

·         Walter Ambrosini (Università di Pisa)

·         Nicola Forgione (Università di Pisa)

 

 

Paper: 560

Study of Supercritical Carbon Dioxide Natural Circulation by the Use of CFD Codes

 

·         Eugenio Molfese (Università di Pisa)

·         Walter Ambrosini (Università di Pisa)

·         Nicola Forgione (Università di Pisa)

·         Pallippattu K. Vijayan (Bhabha Atomic Research Centre)

·         Manish Sharma (Bhabha Atomic Research Centre)

 

 

Paper: 619

Derivation of a Look-Up Table for Trans-Critical Heat Transfer for Water-Cooled Tubes

 

·         Hussam Zahlan (University of Ottawa)

·         De Groeneveld (University of Ottawa)

·         Stavros Tavoularis (University of Ottawa)

 

 

B4-1 Plant System Safety Code Development and Assessment

 

 

Room: Carmichael & Jackson
Session Chair:

·         Tomasz Kozlowski (Royal Institute of Technology)

Session Co-Chair:

·         Kenji Arai (Asahi Kasei Corporation)

 

Paper: 22

Development of a Coupled 1D-3D Thermalhydraulic Code for Nuclear Power Plant Simulation and Its Application to a Pressurized Thermal Shock Scenario in PWR

 

·         Angel Papukchiev (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Georg Lerchl (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Johannes Weis (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Martina Scheuerer (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Henrique Austregesilo (GRS)

 

 

Paper: 46

Advanced ATHLET Model for the UPTF Facility

 

·         Sergey Nikonov (RRC “Kurchatov Institute”)

·         Ihor Pasichnyk (GRS mbH)

·         Kiril Velkov (GRS mbH)

 

 

Paper: 82

Validation of Post-Dryout Phenomena for the Space Code

 

·         Kyung Doo Kim (Korea Atomic Energy Research Institute)

·         S. K. Moon (Korea Atomic Energy Research Institute)

·         B. D. Chung (Korea Atomic Energy Research Institute)

·         B. J. Kim (Korea Atomic Energy Research Institute)

·         S. W. Lee (Korea Atomic Energy Research Institute)

 

 

Paper: 91

Development of a Boiling Model for Application in Lumped-Parameter Codes for Assessment of External Reactor Vessel Cooling

 

·         Ulf Schittek (Ruhr-Universität Bochum)

·         Marco K. Koch (Ruhr-Universität Bochum)

 

 

Paper: 144

Application of ASTEC V2.0 to Severe Accident Analyses for German Konvoi Type Reactors

 

·         Holger Nowack (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Walter Erdmann (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Nils Reinke (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

 

 

Paper: 483

Stratification Criterion for the CATHARE Code

 

·         Guillaume Serre (CEA)

·         Dominique Bestion (Commissariat à l’Énergie Atomique)

·         Maxime Franco (CEA)

·         Manon Bottin (CEA)

·         Muriel Marchand (CEA)

 

 

C3-1 Fuel Coolant Interaction, Modeling and Experiments

 

 

Room: Varley
Session Chair:

·         Georges Jean Berthoud (CEA)

Session Co-Chair:

·         Kwang-Hyun Bang (Korea Maritime University)

 

Paper: 88

Simulation of Bundle Test Quench-12 With Integral Code MELCOR

 

·         Jiri Duspiva (Nuclear Research Institute Rez plc.)

 

 

Paper: 125

Simulation of the Air Ingress Experiment Parameter SF4 Using ATHLET-CD

 

·         Thorsten Hollands (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Christine Bals (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

·         Henrique Austregesilo (GRS)

·         Wolfgang Luther (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)

 

 

Paper: 277

The Effect of Binary Oxide Materials on a Single Droplet Vapor Explosion Triggering

 

·         Roberta Concilio Hansson (Royal Institute of Technology)

·         Louis Tamilarasan Manickam (Royal Institute of Technology)

·         Truc-Nam Dinh (Royal Institute of Technology)

 

 

Paper: 629

Modelling of Solidification Effect in Eulerian Fuel-Coolant Interaction Codes

 

·         Mitja Uršič (Jožef Stefan Institute)

·         Matjaz Leskovar (Jožef Stefan Institute)

 

 

F5-3 Instrumentation Technique

 

 

Room: MacDonald
Session Chair:

·         Stephan Leyer (AREVA NP GmbH)

Session Co-Chair:

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

 

Paper: 435

Ultrasonic Measurement of Water Layer Thickness by Horizontal Flow Pattern Profile in a KAERI HAWL

 

·         Kil-Mo Koo (Korea Atomic Energy Research Institute)

·         Seung-Tae Lee (Korea Atomic Energy Research Institute)

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

 

 

G8-1 Supercritical Water Reactors

 

 

Room: Lismer
Session Chair:

·         Thomas Schulenberg (Karlsruhe Institute for Technology)

Session Co-Chair:

·         Mark Anderson (University of Wisconsin – Madison, Noreddine Mesmous, CNSC)

 

Paper: 316

Thermal Design Aspects of High-Efficiency Channel for SCWRs

 

·         Wargha Peiman (University of Ontario Institute of Technology)

·         Igor Pioro (University of Ontario Institute of Technology)

·         Kamiel Gabriel (University of Ontario Institute of Technology)

 

 

Paper: 491

Analysis of Low Thermal-Conductivity Fuels in a 64-Element SCWR Bundle

 

·         Krysten King (University of Ontario Institute of Technology)

·         Shona Draper (University of Ontario Institute of Technology)

·         Wargha Peiman (University of Ontario Institute of Technology)

·         Ayman Abdalla (University of Ontario Institute of Technology)

·         Arif Qureshi (University of Ontario Institute of Technology)

·         Jon Joel (University of Waterloo)

·         Igor Pioro (University of Ontario Institute of Technology)

·         Kamiel Gabriel (University of Ontario Institute of Technology)

 

 

Paper: 405

Heat Transfer Profiles in a Vertical, Bare, 7-Element Bundle Cooled with Supercritical Freon-12

 

·         Graham Richards (UOIT)

·         A.S. Shelegov (IPPE)

·         P.L. Kirillov (IPPE)

·         Igor Pioro (University of Ontario Institute of Technology)

·         Glenn Harvel (University of Ontario Institute of Technology)

 

 

Paper: 118

Use of a Supercritical Water-Cooled Reactor for Process Heat to Support Thermochemical Hydrogen Production

 

·         Andrew Lukomski (University of Ontario Institute of Technology)

·         Kamiel Gabriel (University of Ontario Institute of Technology)

·         Igor Pioro (University of Ontario Institute of Technology)

 

 

Paper: 86

Options and Challenges of Steam Cycle Components for SCWR

 

·         Thomas Schulenberg (Karlsruhe Institute for Technology)

·         Marc Schlagenhaufer (TÜV SÜD)

·         Heiko Herbell (EnBW Kernkraft GmbH)

 

 

O4-1 BEPU (Best Estimate code Plus Uncertainty) method, CSAU, Statistical Methods

 

 

Room: Harris
Session Chair:

·         Alessandro Petruzzi (GRNSPG, Università di Pisa)

Session Co-Chair:

·         Aleksandar Delja (Canadian Nuclear Safety Commission)

 

Paper: 122

RELAP5 Analysis of Integral Test of the Loss-of-RHR Event During the Mid-Loop Operation

 

·         Minoru Yamada (Institute of Nuclear Safety System, Inc.)

·         Hiroichi Nagumo (MHI Nuclear Engineering Company, Limited)

·         Ikuo Kinoshita (Institute of Nuclear Safety System, Inc.)

 

 

Paper: 187

Simulation of Boiling Water Reactor One-Pump Trip Transient by SIMULATE-3K

 

·         Kenichiro Nozaki (TEPCO Systems)

·         Akitoshi Hotta (TEPCO Systems)

·         Shinya Kosaka (TEPCO Systems)

·         Shoichi Suehiro (TEPCO Systems)

·         Daisuke Fujiwara (TEPCO Systems)

·         Shinya Mizokami (Tokyo Electric Power Company, Inc.)

 

 

Paper: 230

On a Best-Estimate Approach to the Calculation of Dryout Probability During BWR Transients

 

·         Carl Adamsson (Westinghouse Electric Sweden AB)

·         Jean-Marie Le Corre (Westinghouse Electric Sweden AB)

 

 

Paper: 242

Application of Wavelet Transforms as a Time-Series Analysis Tool for Nuclear Thermalhydraulics

 

·         Daniel J. Pohl (AMEC NSS )

·         Adrian I. Popescu (AMEC NSS )

·         Jason Pascoe (AMEC NSS )

 

 

Paper: 330

Investigation of the Uncertainty of Governing Equation Systems in Thermalhydraulic Calculation

 

·         Tomasz Skorek (Gesellschaft fuer Anlagen- und Reaktorsicheheit mbH)

·         Bernhard Krzykacz-Hausmann (Gesellschaft fuer Anlagen- und Reaktorsicheheit mbH)

·         Henrique Austregesilo (GRS)

 

 

Paper: 344

The BEPU (Best Estimate Plus Uncertainty) Challenge in Current Licensing of Nuclear Reactors

 

·         Alessandro Petruzzi (GRNSPG, Università di Pisa)

·         Nikolaus Muellner (GRNSPG, Università di Pisa)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

·         Oscar Mazzantini (Nucleoeléctrica Argentina S.A.)

 

 

A7-1 Mini Symposium on Flow-induced Vibration in Nuclear Components

 

 

Room: Toronto II
Session Chair:

·         Marwan Hassan (University of New Brunswick)

Session Co-Chair:

·         David Weaver (McMaster University)

 

Paper: 35

A Simple Model for Two-Phase Slug Flow Induced Damping

 

·         Njuki Mureithi (Ecole Polytechnique)

·         Teguewinde Sawadogo (Ecole Polytechnique)

·         Fabien Bernard (ENSEEIHT)

 

 

Paper: 73

Investigations on Flow Induced Vibration of Simulated CANDU Fuel Bundles in a Pipe

 

·         Xuan Zhang (Ryerson University)

·         Shudong Yu (Ryerson University)

 

 

Paper: 159

Modeling of Fuel Bundle Vibration and the Associated Fretting Wear in a CANDU Fuel Channel

 

·         Atef Mohany (University of New Brunswick)

·         Marwan Hassan (University of New Brunswick)

 

 

Paper: 160

Numerical Investigation of Flow-Induced Vibration and Fretting Wear Potential of Multi-Span U-Tubes with Clearance Supports

 

·         Marwan Hassan (University of New Brunswick)

·         Atef Mohany (University of New Brunswick)

 

 

Paper: 201

Unsteady Hydraulic Characteristics in Pipe with Elbow Under High Reynolds Condition

 

·         Ayako Ayako (Japan Atomic Energy Agency)

·         Nobuyuki Nobuyuki (Japan Atomic Energy Agency)

·         Hideki Hideki (Japan Atomic Energy Agency)

·         Akira Tobita (Japan Atomic Energy Agency)

 

 

Paper: 211

Finite Mixture Model Applied in the Analysis of a Turbulent Bistable Flow on Two Parallel Circular Cylinders

 

·         Alexandre De Paula (UFRGS - Federal University of Rio Grande do Sul)

·         Sergio Möller (Federal University of Rio Grande do Sul)

 

 

B2-1 Computational Multi-Fluid Dynamics and Validation/Verification/Applications

 

 

Room: Tom Thomson
Session Chair:

·         Guan Heng Yeoh (ANSTO)

Session Co-Chair:

·         Akitoshi Hotta (TEPCO Systems)

 

Paper: 67

Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg Using VOF Method

 

·         Michio Murase (Institute of Nuclear Safety System, Inc.)

·         Ikuo Kinoshita (Institute of Nuclear Safety System, Inc.)

·         Chihiro Yanagi (Institute of Nuclear Safety System, Inc.)

·         Takashi Takata (Osaka University)

·         Akira Yamaguchi (Osaka University)

·         Akio Tomiyama (Kobe University)

 

 

Paper: 70

Core Radial Profile Effect During Reflooding, Validation of CATHARE2 3D Module Using SCTF Tests

 

·         Isabelle Dor (CEA)

·         Philippe Germain (CEA)

 

 

Paper: 75

The Importance of Correct Modeling of Bubble Size and Condensation in Prediction of Sub-Cooled Boiling Flows

 

·         Simon Lo (CD-adapco)

·         Andrew Splawski (CD-adapco)

·         Byong Jo Yun (Korea Atomic Energy Research Institute)

 

 

Paper: 101

Verification and Validation of Numerical Models of the Transport of Insulation Debris

 

·         Gregory M. Cartland Glover (Helmholtz-Zentrum Dresden-Rossendorf)

·         Alexander Kratzsch (Hochschule Zittau/Goerlitz)

·         Eckhard Krepper (Helmholtz-Zentrum Dresden-Rossendorf)

·         Stefan Renger (Hochschule Zittau/Goerlitz)

·         André Seeliger (Hochschule Zittau/Goerlitz)

·         Frank Zacharias (Hochschule Zittau/Goerlitz)

·         Sören Alt ((University of Applied Sciences Zittau//Goerlitz))

·         Wolfgang Kästner (Hochschule Zittau/Goerlitz)

·         Holger Kryk (Helmholtz-Zentrum Dresden-Rossendorf)

·         Frank-Peter Weiss (Helmholtz-Zentrum Dresden-Rossendorf)

 

 

Paper: 240

Two-Dimensional Simulation of the Downcomer Boiling Experiment Using the CUPID Code

 

·         Hyoung Kyu Cho (Korea Atomic Energy Research Institute)

·         Byong Jo Yun (Korea Atomic Energy Research Institute)

·         Jae Ryong Lee (Korea Atomic Energy Research Institute)

·         Han Young Yoon (Korea Atomic Energy Research Institute)

·         Jae Jun Jeong (Pusan National University)

 

 

Paper: 253

Evaporation over Sump Surface in Containment Studies: Code Validation on TOSQAN Tests

 

·         Jeanne Malet (IRSN)

·         Thomas Gelain (IRSN)

·         Olivier Degrees Du Lou (IRSN/ENSAM)

·         Virginie Daru (ENSAM/LIMSI)

 

 

B13-4 Development, Assessment and Applications of TRACE

 

 

Room: Carmichael & Jackson
Session Chair:

·         Kenji Arai (Asahi Kasei Corporation)

Session Co-Chair:

·         Tomasz Kozlowski (Royal Institute of Technology)

 

Paper: 9

On the Evaluation of the Pressure Losses in a Lead-Bismuth-Eutectics Cooled Fuel Assembly with TRACE and SUSA

 

·         Wadim Jaeger (Karlsruhe Institute of Technology)

·         Victor Sánchez Espinoza (Karlsruhe Institute for Technology)

 

 

Paper: 476

Testing of the Quickest-Ultimate Algorithm to Solve the Dissolved Convection Equation During a Boron Dilution Test at the PKL Facility

 

·         Jordi Freixa (Paul Scherrer Institut)

·         Davide Bertolotto (Paul Scherrer Institut)

·         Annalisa Manera (Paul Scherrer Institut)

 

 

Paper: 612

OECD/NEA Main Steam Line Break PWR Benchmark Simulation by TRACE/S3K Coupled Code

 

·         Konstantin Nikitin (Paul Scherrer Institut)

·         Annalisa Manera (Paul Scherrer Institut)

·         Hakim Ferroukhi (Paul Scherrer Institut)

·         Jerry Judd (Studsvik Scandpower, Inc.)

·         Gerardo M. Grandi (Studsvik, Idaho Falls)

 

 

Paper: 577

MARS-KS Assessment of TRACE Fundamental Problems

 

·         Won Joon Chang (KINS)

·         D.-H. Yoon (KINS)

·         N. S. Kim (KINS)

·         S. Y. An (KINS)

·         B. S. Shin (KINS)

·         S. H. Ahn (KINS)

 

 

Paper: 513

PATHS: a Steady State Two-Phase Thermalhydraulic Solver for PARCS Depletion

 

·         Benjamin Collins (University of Michigan)

·         Linsen Li (University of Michigan)

·         Shane Stimpson (University of Michigan)

·         Daniel Jabaay (University of Michigan)

·         Andrew Ward (University of Michigan)

·         Yunlin Xu (University of Michigan)

·         Thomas Downar (University of Michigan)

·         Dean Wang (Oak Ridge National Laboratory)

 

 

F1-1 Boiling and Condensation Heat Transfer

 

 

Room: Varley
Session Chair:

·         Shripad Revankar (Purdue University)

Session Co-Chair:

·         Wan Pak (CNSC)

 

Paper: 36

Experimental Investigation of Air Bubble Flows in a Water Pool

 

·         Benjamin Balewski (Becker Technologies GmbH)

·         Sanjeev Gupta (Becker Technologies GmbH)

·         Karsten Fischer (Becker Technologies GmbH)

·         Gerhard Poss (Becker Technologies GmbH)

 

 

Paper: 241

Two-Phase Swirling Flow in a Barrel of a Steam Separator

 

·         Kenichi Katono (Hitachi, Ltd.)

·         Toshiki Matsubayashi (Kobe University)

·         Koji Nishida (Hitachi, Ltd.)

·         Akio Tomiyama (Kobe University)

 

 

Paper: 320

Reproducibility of Heat Transfer Tests in a 5X5 Bundle Geometry

 

·         Geraud Cubizolles (Commissariat à l'Energie Atomique)

·         Philippe Clement (Commissariat à l'Energie Atomique)

·         Dionysius Groeneveld (University of Ottawa)

 

 

E3-1 Instabilities and Nonlinear Dynamics

 

 

Room: MacDonald
Session Chair:

·         Jens G. Andersen (GE Hitachi Nuclear Energy)

Session Co-Chair:

·         Jacek Schumanski (CNSC)

 

Paper: 164

The Stability Analysis of LAPUR6 for Chinshan BWR Nuclear Power Plant

 

·         Jong-Rong Wang (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Hao-Tzu Lin (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)

·         Chunkuan Shih (National Tsing Hua University)

 

 

Paper: 216

Study of Density Wave Phenomena in Boiling and Condensing Two-Phase Flow Systems

 

·         Leonardo Ruspini (Norwegian University of Science and Technology)

·         Carlos Dorao (Norwegian University of Science and Technology)

·         Maria Fernandino (Norwegian University of Science and Technology)

 

 

Paper: 217

Study of Inertia Effects on Density Wave Oscillations in Two-Phase Systems

 

·         Leonardo Ruspini (Norwegian University of Science and Technology)

 

 

Paper: 256

The Kelvin-Helmholtz Instability: Comparisons of One- and Two-Dimensional Simulations

 

·         William Fullmer (Purdue University)

·         Martin Lopez De Bertodano (Purdue University)

·         Victor Ransom (Purdue University)

 

 

Paper: 502

Parametric Study of Different Perturbations on Ringhals Stability Benchmark With RELAP5/PARCS Coupled Code

 

·         Agustin Abarca (Universidad Politécnica de Valencia)

·         Teresa Barrachina (Universidad Politécnica de Valencia)

·         Rafael Miró (Universidad Politécnica de Valencia)

·         Damián Ginestar (Universidad Politécnica de Valencia)

·         Gumersindo Verdú (Universidad Politécnica de Valencia)

 

 

G8-2 Supercritical Water Reactors

 

 

Room: Lismer
Session Chair:

·         Sama Bilbao y Leon (Virginia Commonwealth University)

Session Co-Chair:

·         Igor Pioro (University of Ontario Institute of Technology)

 

Paper: 202

Safety Analyses for a SCWR In-Pile Fuel Assembly Test

 

·         Manuel Raqué (Karlsruhe Institute for Technology)

·         Ivan Vasari (TÜV Süd Energietechnik GmBH)

·         Thomas Schulenberg (Karlsruhe Institute for Technology)

 

 

Paper: 123

Stability Research on a Natural Circulation Driven SCWR

 

·         Christophe Tjoen (Delft University of Technology)

·         Frederik Kam (Delft University of Technology)

·         Martin Rohde (Delft University of Technology)

 

 

Paper: 331

Experimental Investigations on the Steady State and Stability Behaviour of Supercritical Pressure Natural Circulation

 

·         Pallipattu Krishnan Vijayan (Bhabha Atomic Research Centre)

·         S.B. Thakuria (Homi Bhabha National Institute)

·         Manish Sharma (Bhabha Atomic Research Centre)

·         D.S. Pilkhwal

·         D. Saha (Bhabha Atomic Research Centre)

·         R. K. Sinha (Bhabha Atomic Research Centre)

 

 

Paper: 264

Effect of Properties of Fluids at Supercritical Pressures on Flow-Induced Instabilities

 

·         Tara Gallaway (RPI)

·         Michael Podowski (RPI)

 

 

O4-2 BEPU (Best Estimate code Plus Uncertainty) method, CSAU, Statistical Methods

 

 

Room: Harris
Session Chair:

·         Michio Murase (Institute of Nuclear Safety System, Inc.)

Session Co-Chair:

·         Jinzhao Zhang (Tractebel Engineering)

 

Paper: 371

Uncertainty Analysis of the 35% Reactor Inlet Header Break in a CANDU 6 Reactor Using RELAP/SCDAPSIM/MOD4.0 with Integrated Uncertainty Analysis Option

 

·         Daniel Dupleac (Politehnica University of Bucarest)

·         Marina Pérez (Technical University of Catalonia)

·         Francesc Reventós (Universitat Politécnica de Catalunya)

·         Chris Allison (Innovative Systems Software)

 

 

Paper: 409

Scaling, Experiment, and Code Validation on an Integral Testing Facility

 

·         Jun Yang (Purdue University)

·         Sung Won Choi (Purdue University)

·         Jaehyok Lim (Purdue University)

·         Doo Yong Lee (Purdue University)

·         Somboon Rassame (Purdue University)

·         Takashi Hibiki (Purdue University)

·         Mamoru Ishii (Purdue University)

 

 

Paper: 465

Quantitative Analysis of Safety Margin Reduced by Power Uprate in SBLOCA

 

·         Yu Min Chen (National Tsing Hua University, Hsinchu, Taiwan)

·         Min Lee (National Tsing Hua University, Hsinchu, Taiwan)

·         Jyh Der Lin (Institute of Nuclear Energy Research, Taoyuan, Taiwan)

 

 

Paper: 470

Post-Test Thermalhydraulic Analysis of Two Intermediate LOCA Tests at the ROSA Facility Including Uncertainty Evaluation

 

·         Jordi Freixa (Paul Scherrer Institut)

·         Tae-Wan Kim (Paul Scherrer Institut)

·         Annalisa Manera (Paul Scherrer Institut)

 

 

Paper: 514

RELAP5 Based Subchannel Analysis for Licensing of Atucha2 NPP

 

·         Nikolaus Muellner (GRNSPG, Università di Pisa)

·         Pablo Camusso (Nucleoeléctrica Argentina S.A.)

·         Oscar Mazzantini (Nucleoeléctrica Argentina S.A.)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

 

 

Paper: 345

Error Sources Considered in the "UMAE Driven" CIAU Methodology

 

·         Andriy Kovtonyuk (GRNSPG, Università di Pisa)

·         Alessandro Petruzzi (GRNSPG, Università di Pisa)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

 

 

A9-3 Interfacial Area Transport - Computational

 

 

Room: Toronto II
Session Chair:

·         Mori Michitsugu (Meiji University)

Session Co-Chair:

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

 

Paper: 51

Numerical Simulation of an Air-Water Counter-Current Two-Phase Flow Experiment in a PWR Hot Leg Model Using an Interfacial Area Density Model

 

·         Thomas Hoehne (HZDR)

·         Deen Darlianto (HZDR)

·         Christophe Vallée (HZDR)

·         Dirk Lucas (HZDR)

·         Matthias Beyer (HZDR)

 

 

Paper: 87

Coupling of Wall Boiling with Discrete Population Balance Model

 

·         Conxita Lifante (ANSYS Germany)

·         Florian Reiterer (ANSYS Germany)

·         Thomas Frank (ANSYS Germany)

·         Alan Burns (ANSYS UK Ltd.)

 

 

Paper: 373

Prediction of Adiabatic Bubbly Flows in TRACE Using the Interfacial Area Transport Equation

 

·         Justin Talley (The Pennsylvania State University)

·         Ted Worosz (The Pennsylvania State University)

·         Seungjin Kim (The Pennsylvania State University)

·         John H. Mahaffy (U.S. Nuclear Regulatory Commission)

·         Stephen M. Bajorek (U.S. Nuclear Regulatory Commission)

·         Kirk Tien (U.S. Nuclear Regulatory Commission)

 

 

Paper: 519

Modeling Bubbly-Cap Flows Using Two-Group Average Bubble Number Density

 

·         Guan Heng Yeoh (ANSTO)

·         Sherman Cheung (RMIT University)

·         Jiyuan Tu (RMIT University)

·         Eckhard Krepper (Helmholtz-Zentrum Dresden-Rossendorf)

·         Dirk Lucas (HZDR)

 

 

B2-2 Computational Multi-Fluid Dynamics and Validation/Verification/Applications

 

 

Room: Tom Thomson
Session Chair:

·         Martin Bertodano (Purdue University)

Session Co-Chair:

·         Guan Heng Yeoh (ANSTO)

 

Paper: 294

Two-Dimenional Three-Regions Rewetting Modelling Using ANSYS

 

·         Muhammad Ilyas (Pakistan Institute of Engineering and Applied Sciences)

·         Simon Walker (Imperial College London)

·         Geoff Hewitt (Imperial College London)

 

 

Paper: 433

Analysis of Reacting Gas Jets in Liquid Pools Using the SERAPHIM Program

 

·         Akihiro Uchibori (Japan Atomic Energy Agency)

·         Akira Watanabe (NDD corporation)

·         Hiroyuki Ohshima (Japan Atomic Energy Agency)

 

 

Paper: 436

Development of Direct Steam-Water Phase Change Analysis Method Applying to BWR Operating Condition

 

·         Masato Fukuta (Toshiba Corporation)

·         Yasushi Yamamoto (Toshiba Corporation)

·         Toru Mitsutake (Toshiba Corporation)

 

 

Paper: 590

CFD Simulation of Adiabatic Two-Phase Flow in the Cap Bubble Regime Using the Two-Group Interfacial Area Transport Equations (IATE)

 

·         Deoras Prabhudharwadkar (Purdue University)

·         Martin Lopez De Bertodano (Purdue University)

·         John Buchanan (Bechtel Marine Propulsion Corporation, Bettis Laboratory)

·         Paul Guilbert (ANSYS UK Ltd.)

 

 

E6-1 Safety Analysis of Sodium Cooled, RBMK and VVER Reactors

 

 

Room: Carmichael & Jackson
Session Chair:

·         Luca Ammirabile (European Commission, JRC, Institute for Energy)

Session Co-Chair:

·         Richard Schultz (INEEL)

 

Paper: 390

Dynamic Scenario Quantification Based on Continuous Markov Monte Carlo Method With Meta-Model of Thermalhydraulics for Level 2 PSA

 

·         Satoshi Shinzaki (Osaka University)

·         Akira Yamaguchi (Osaka University)

·         Takashi Takata (Osaka University)

·         Hiroshi Endo (Japan Nuclear Energy Safety Organization)

·         Tomoko Ishizu (Japan Nuclear Energy Safety Organization)

 

 

Paper: 443

Analysis of Phenix Core Response to Inlet Sodium Temperature Increase During One of the EOL Tests

 

·         Aurelia Chenu (PSI, EPFL)

·         Konstantin Mikityuk (Paul Scherrer Institut)

·         Robert Adams (PSI, ETHZ)

·         Rakesh Chawla (PSI, EPFL)

 

 

Paper: 456

Thermalhydraulic Analyses for Optimization of Hydroaccumulators Parameters in VVER-440

 

·         Pavel Kral (UJV Rez)

 

 

Paper: 473

Sump Strainer Performance Experiments for VVER-440

 

·         Jani Laine (Lappeenranta University of Technology)

·         Antti Räsänen (Lappeenranta University of Technology)

·         Heikki Purhonen (Lappeenranta University of Technology)

 

 

D5-1 Fluid and Structures Mechanical Interactions

 

 

Room: Varley
Session Chair:

·         Milorad Dzodzo (Westinghouse Electric Company)

Session Co-Chair:

·         Yanpeng Wang (CNSC)

 

Paper: 129

Experimental Setup for the Investigation of Fluid-Structure Interactions in a T-Junction

 

·         Mario Kuschewski (IKE)

·         Rudi Kulenovic (Institute of Nuclear Technology and Energy Systems, Universität Stuttgart)

·         Eckart Laurien (Institute for Nuclear Technology and Energy Systems (IKE))

 

 

Paper: 139

CFD Simulations of Ballooned Regions of a Damaged Core During the Reflood Phase of a LOCA

 

·         Nathalie Seiler (IRSN)

·         Pierre Ruyer (IRSN)

·         Franck Lelong (IRSN)

·         Federica Secondi (IRSN)

·         Michel Gradeck (CNRS)

 

 

Paper: 140

Thermalhydraulic Subchannel Analysis in Ballooned Regions of a Damaged Core During the Reflood Phase of a LOCA

 

·         Nathalie Seiler (IRSN)

·         Pierre Ruyer (IRSN)

·         Bryan Biton (IRSN)

 

 

Paper: 573

Investigation of Fluid Structure Interaction in Thin Fluid Gaps - Comparison Between CFD and Experiment.

 

·         Jan-Patrice Simoneau (AREVA)

 

 

B7-1 Steam Generators Thermalhydraulics

 

 

Room: MacDonald
Session Chair:

·         Heather Feldman (Electric Power Research Institute)

Session Co-Chair:

·         Sanja Simic (CNSC)

 

Paper: 119

Break Size Effect on the Transient Thermalhydraulic Behaviour During the Steam Generator Tube Rupture Accident

 

·         Kyoung-Ho Kang (Korea Atomic Energy Research Institute)

·         Hyun-Sik Park (Korea Atomic Energy Research Institute)

·         Seok Cho (Korea Atomic Energy Research Institute)

·         Nam-Hyun Choi (Korea Atomic Energy Research Institute)

·         In-Cheol Chu (Korea Atomic Energy Research Institute)

·         Byong Jo Yun (Korea Atomic Energy Research Institute)

·         Kyung-Doo Kim (Korea Atomic Energy Research Institute)

·         Yeon-Sik Kim (Korea Atomic Energy Research Institute)

·         Won-Pil Baek (Korea Atomic Energy Research Institute)

·         Ki-Yong Choi (Korea Atomic Energy Research Institute)

 

 

Paper: 120

Thermalhydraulic System Analysis Using the MARS Code for the Transient Steam Generator Tube Rupture Accident

 

·         Kyoung-Ho Kang (Korea Atomic Energy Research Institute)

·         Seung-Wook Lee (Korea Atomic Energy Research Institute)

·         Sung-Won Bae (Korea Atomic Energy Research Institute)

·         Won-Pil Baek (Korea Atomic Energy Research Institute)

·         Ki-Yong Choi (Korea Atomic Energy Research Institute)

 

 

Paper: 321

Deposit Model for Tube Support Plate Blockage in Steam Generators

 

·         Thomas Prusek (Electricité de France)

·         Edgar Moleiro (Electricité de France)

·         Fadila Oukacine (Electricité de France)

·         Ouardia Touazi (Electricité de France)

·         Marc Grandotto (M2P2 - UMR-6181, CEA Cadarache)

·         Marc Jaeger (Aix-Marseille Université, CNRS, Ecole Centrale Marseille)

·         André Adobes (Electricité de France)

 

 

O1-2 Thermalhydraulics and Structural Integrity in Connection to Aging and Life Extension

 

 

Room: Lismer
Session Chair:

·         Masanori Naitoh (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

Session Co-Chair:

·         Akio Tomiyama (Kobe University)

 

Paper: 523

Development of a CANDU Fuel Channel Model to Assess the Effect of a Pressure Tube Creep on the Safety Related Parameters

 

·         Bo Rhee (Korea Atomic Energy Research Institute)

·         Hyoung Tae Kim (Korea Atomic Energy Research Institute)

·         Joo Hwan Park (Korea Atomic Energy Research Institute)

·         Y.G. Jo (KAIST)

 

 

Paper: 542

Flow Accelerated Corrosion and Mass Transfer Rate in Orifice Downstream Flow

 

·         Retsu Kojo (Nagoya University)

·         Yuji Kuroda (Nagoya University)

·         Masaya Kondo (Nagoya University)

·         Yoshiyuki Tsuji (Nagoya University)

 

 

Paper: 624

Evaluation Method for Pipe Wall Thinning Due to Liquid Droplet Impingement - (I) Overview

 

·         Masanori Naitoh (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Shunsuke Uchida (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Hidetoshi Okada (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Hiroaki Yugo (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Seiichi Koshizuka (The University of Tokyo)

 

 

Paper: 626

Evaluation Method for Pipe Wall Thinning Due to Liquid Droplet Impingement - (II) Comparison of Calculations with Measurements at Actual Nuclear Power Plants

 

·         Hidetoshi Okada (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Shunsuke Uchida (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Hiroaki Yugo (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Masanori Naitoh (Nuclear Power Engineering Center, Safety Analysis Group, The Institute of Applied Energy)

·         Seiichi Koshizuka (The University of Tokyo)

 

 

O4-3 BEPU (Best Estimate code Plus Uncertainty) method, CSAU, Statistical Methods

 

 

Room: Harris
Session Chair:

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

Session Co-Chair:

·         Michio Murase (Institute of Nuclear Safety System, Inc.)

 

Paper: 536

Accuracy Assessments with Fast Fourier Transform Based Method (FFTBM)

 

·         Eugenio Coscarelli (GRNSPG, Università di Pisa)

·         Alfredo Raimato (University of Pisa)

·         Dino Araneo (University of Pisa, GRNSPG, Italy)

·         Marco Cherubini (University of Pisa)

·         Nikolaus Muellner (GRNSPG, Università di Pisa)

·         Francesco S. D'Auria (University of Pisa, GRNSPG, Italy)

 

 

Paper: 603

A Best-Estimate Plus Uncertainty Type Analysis for Computing Accurate Critical Channel Power Uncertainties

 

·         Dan Quach (AMEC NSS)

·         Paul Sermer (AMEC NSS)

·         Fred Hoppe (McMaster University)

·         Ovidiu Nainer (Bruce Power)

·         Bac Phan (Ontario Power Generation)

 

 

Paper: 616

Errors in Mean and Fluctuating Velocity Due to PIV Bias and Precision Uncertainties

 

·         Brandon Wilson (USU)

·         Barton Smith (USU)

 

 

Paper: 95

Extended Forward Sensitivity Analysis for Uncertainty Quantification

 

·         Haihua Zhao (Idaho National Laboratory)

·         Vincent Mousseau (Idaho National Laboratory)

 

 

CNSC – KINS Cooperative Research Meeting

 

 

Room: 9
Session Chair:

·         Aleksandar Delja (Canadian Nuclear Safety Commission)

 

Morning Committee Meetings 1 Generation IV International Forum (GIF) Super Critical Water Reactors (SCWR) Thermalhydraulics and Safety Project Management Board

 

 

Room: Toronto II

 

A9-2 Interfacial Area Transport - Experimental

 

 

Room: Toronto II
Session Chair:

·         Stephen M. Bajorek (U.S. Nuclear Regulatory Commission)

Session Co-Chair:

·         Dominique Bestion (Commissariat à l’Énergie Atomique)

 

Paper: 157

Experimental Study of Two-Phase Flows Under Reduced Gravity Conditions

 

·         Tirthankar Roy (Norwegian University of Science and Technology)

·         Yang Liu (Purdue University)

·         Shao-Wen Chen (Purdue University)

·         Takashi Hibiki (Purdue University)

·         Mamoru Ishii (Purdue University)

·         Walter Duval (NASA Glenn Research Center)

 

 

Paper: 193

Measurement of Film Dynamics in a Boiling Liquid Film

 

·         Shengjie Gong (Royal Institute of Technology)

·         Weimin Ma (Royal Institute of Technology)

·         Truc-Nam Dinh (Royal Institute of Technology)

 

 

Paper: 374

The Effect of Bubble-Induced Turbulence and the Bubble Size on the Interfacial Area Transport in Gas-Liquid Two-Phase Flow

 

·         Van-Thai Nguyen (Korea Atomic Energy Research Institute)

·         Byoung-Uhn Bae (Korea Atomic Energy Research Institute)

·         Dong-Jin Euh (Korea Atomic Energy Research Institute)

·         Chul-Hwa Song (Korea Atomic Energy Research Institute)

 

 

Paper: 384

Geometric Effects of 90-Degree Vertical Elbows on Global Two-Phase Flow Parameters

 

·         Mohan Yadav (The Pennsylvania State University)

·         Seungjin Kim (The Pennsylvania State University)

 

 

Paper: 385

Local Interfacial Structures and Interfacial Area Transport Modeling Across 90-Degree Vertical Elbows

 

·         Mohan Yadav (The Pennsylvania State University)

·         Ted Worosz (The Pennsylvania State University)

·         Seungjin Kim (The Pennsylvania State University)

 

 

B1-1 Computational Fluid Dynamics, Mathematical Modeling and Verification/Validation/Applications

 

 

Room: Tom Thomson
Session Chair:

·         Yasuo Koizumi (Shinshu University)

Session Co-Chair:

·         Slavko Vasic (CNSC)

 

Paper: 33

Large Eddy and Interface Simulation (LEIS) of Liquid Entrainment in Turbulent Stratified Flow

 

·         Saaransh Gulati (Massachusetts Institute of Technology)

·         Jacopo Buongiorno (Massachusetts Institute of Technology)

·         Djamel Lakehal (MIT, ASCOMP Gmbh, Switzerland)

 

 

Paper: 62

Developments in Single Phase Fuel Assembly Simulations

 

·         Ferry Roelofs (NRG)

·         Vinay R. Gopala (NRG)

·         Dirk Visser (NRG)

·         Afaque Shams (NRG)

·         Jan-Aiso Lycklama À Nijeholt (ECN)

·         Laltu Chandra (IIT Rajasthan)

 

 

Paper: 158

Large Eddy Simulation of Turbulent Flows in Compound Channels with a Finite Element Code

 

·         Carla Xavier (Federal University of Rio Grande do Sul)

·         Adriane Petry (Federal University of Rio Grande do Sul)

·         Sergio Möller (Federal University of Rio Grande do Sul)

 

 

Paper: 168

Effect of Reynolds Number and Bundle Geometry on the Turbulent Flow in Tight Lattice Bundle

 

·         Yiqi Yu (Shanghai Jiao Tong University)

·         Xu Cheng (Shanghai Jiao Tong University)

 

 

Paper: 173

Computational Study of Turbulent Heat Transfer for Heating of Water in a Short Vertical Tube Under Velocities Controlled

 

·         Koichi Hata (Institute of Advanced Energy, Kyoto University)

·         Naoto Kai (Kyoto University)

·         Yasuyuki Shirai (Kyoto University)

·         Suguru Masuzaki (National Institute for Fusion Science)

·         Akimichi Hamura (Concentration Heat and Momentum Ltd.)

 

 

Paper: 204

Fluid Flow and Heat Transfer Investigation of Pebble Bed Reactors Using Mesh-Adaptive Large-Eddy Simulation

 

·         Dimitrios Pavlidis (Delft University of Technology)

·         Danny Lathouwers (Delft University of Technology)

 

 

B12-1 Minisymposium on Pressure Surges in Nuclear Power Plants

 

 

Room: Carmichael & Jackson
Session Chair:

%0

 

The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics

Product Type : Business Conference

Author : Canadian Nuclear Society

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Languages : English

Organizer : Canadian Nuclear Society

The CNS is dedicated to the exchange of information, both within the nuclear professional and academic community, and with the public, in the field of applied nuclear science and technology. This encompasses all aspects of nuclear energy, uranium, fission and other nuclear technologies such as occupational and environmental protection, medical diagnosis and treatment, the use of radioisotopes, and food preservation.