2011: The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics | Proceedings of the Canadian Nuclear Society

Ferry Roelofs, Yassin A. Hassan, Emilio Baglietto, Djamel Lakehal, Walter Ambrosini, Diego Angeli, Laurent Bricteux, Bojan Niceno, Henryk Anglart, Iztok Tiselj, Guillaume Brillant, Ivan Otic, Martin Rohde, Xu Cheng

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

Mario Kuschewski, Rudi Kulenovic, Eckart Laurien

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Mechanistic Modeling of Critical Heat Flux on a CANDU Calandria Tube Following Pressure Tube Contact

Azin Behdadi, John C. Luxat

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

Xi-Qing Chen, Ab Tahir, Y. Parlatan, M. Kwee

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

Yuzhou Chen, Chunsheng Yang, Minfu Zhao, Keming Bi, Kaiwen Du, Shuming Zhang

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A Model for Droplet Entrainment Rate in Horizontal Stratified Flow

François Henry, Valette Michel, Yann Bartosiewicz

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

Nathalie Seiler, Pierre Ruyer, Franck Lelong, Federica Secondi, Michel Gradeck

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Eulerian Simulation of Interacting PWR Sprays: Influence of Droplet Collisions

Arnaud Foissac, Jeanne Malet, Stephane Mimouni, Pierre Ruyer, François Feuillebois, Olivier Simonin

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

Abdalla Batta, Andreas G. Class

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Analysis of a German BWR Core with TRACE/PARCS Using Different Cross Section Sets

Christoph Hartmann, Victor H. Sanchez, Wolfgang Tietsch

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

Aurelian Tanase, Dionysius Groeneveld, Hussam Zahlan

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

A. Shams, Dirk C. Visser, Ferry Roelofs

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

Nathalie Seiler, Pierre Ruyer, Bryan Biton

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

Yoonyeong Bae, Sung Deok Hong, Yong Wan Kim

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

Jan-Patrice Simoneau, N. Jobert, F. Jeandenans

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Validation and Application of TRACE for Transient Analysis of a German BWR Plant

Victor H. Sanchez, Marc Thieme, Wolfgang Tietsch

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

G.H. Lee, S.W. Woo

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

Djamel Lakehal, Jarunan Panyasantisuk, D. Caviezel, M. Labois, Chidambaram Narayanan

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

Kyoung-Ho Kang, Won-Pil Baek, Yeon-Sik Kim, Kyung Doo Kim, Byong Jo Yun, In-Cheol Chu, Nam-Hyun Choi, Seok Cho, Hyun-Sik Park, Ki-Yong Choi

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Validation of TRACE Code for Type-I Density Wave Oscillations in SIRIUS-N Facility, which Simulates ESBWR

Masahiro Furuya, Yoshihisa Nishi, Nobuyuki Ueda

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Elements of Validation for LWRs Thermalhydraulic Studies With FLICA-OVAP

Philippe Fillion, Matteo Bucci, Anne Charmeau

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

Emilio Baglietto

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

Kyoung-Ho Kang, Seung-Wook Lee, Sung-Won Bae, Won-Pil Baek, Ki-Yong Choi

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TRACE/PARCS Validation for BWR Stability Based on OECD/NEA Oskarshamn-2 Benchmark

Tomasz Kozlowski, Christer Netterbrant, Matthew Hardgrove, Jeffrey Magedanz, Kostadin Ivanov, Aaron Wysocki, Yunlin Xu, Thomas Downar, Tomas Lefvert, Sean Roshan, Jose March-Leuba

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

Serge Bellet, Sofiane Benhamadouche, A. Ferret

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

Ki-Yong Choi, Won-Pil Baek, Hyun-Sik Park, Seok Cho, Kyoung-Ho Kang, Yeon-Sik Kim

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Deposit Model for Tube Support Plate Blockage in Steam Generators

Thomas Prusek, Edgar Moleiro, Fadila Oukacine, Ouardia Touazi, Marc Grandotto, Marc Jaeger, Andre Adobes

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TRACE Code Validation for BWR Spray Cooling Injection Based on GÖTA Facility Experiments

Stefano Racca, Tomasz Kozlowski

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CFD Model of CANDU Calandria Vessel Retention During Severe Accidents

Fei Song, Boris Lekakh, Ken Hau

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

Bo-Wook Rhee, Hyoung Tae Kim, Joo Hwan Park, Y.G. Jo

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Prediction of Specimen Temperatures During Irradiation of a New Composite Material

Donna Post Guillen, W. David Wank, Adam X. Zabriskie, Heng Ban

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

Jae Ryong Lee, Rae-Joon Park, Seong Wan Hong

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Multidimensional Boron Transport Modeling in Subchannel Approach

Ozkan Ozdemir, Maria Avramova, Kenya Sato

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

Patricia Pla, Carlo Parisi, Regina Galetti, Francesco S. D'Auria, Giorgio Galassi, Francesc Reventos

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Flow Accelerated Corrosion and Mass Transfer Rate in Orifice Downstream Flow

Retsu Kojo, Yuji Kuroda, Masaya Kondo, Yoshiyuki Tsuji

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Application of the Ballooning Analysis Code MATARE on a Generic PWR Fuel Assembly

Luca Ammirabile, Simon Walker

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

Tae Il Kim, Hae Min Park, Soon Heung Chang

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DNB Prediction Using Local Void Distribution in High Quality Flow

Tatsuya Sasakawa, Tsutomu Ikeno, Isao Kataoka

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

Leonhard Meyer, Giancarlo Albrecht

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

Rade Milenkovic, Sergejs Dementjevs

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

Masanori Naitoh, Shunsuke Uchida, Hidetoshi Okada, Hiroaki Yugo, Seiichi Koshizuka

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

Poo Balan Ganesan, Shuisheng He, Faik Hamad, Jim Gotts

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

Hidetoshi Okada, Shunsuke Uchida, Hiroaki Yugo, Masanori Naitoh, Seiichi Koshizuka

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In-Subchannel Two-Dimensional Flow Structure Induced by Bubble-Liquid Interfacial Forces

Tsutomu Ikeno, Tatsuya Sasakawa, Isao Kataoka

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

Shao-Shuan Chen, Tsung-Sheng Feng, Kai-Chun Huang, Jong-Rong Wang, Y.H. Cheng, Chunkuan Shih

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Validation of the Condensation Model for Containment Thermalhydraulics

R. Srinivasa Rao, Teany Thomas, Kannan N. Iyer, S.K. Gupta

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

A. Gandhir, Yassin A. Hassan

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Accuracy Assessments with Fast Fourier Transform Based Method (FFTBM)

Eugenio Coscarelli, Alfredo Raimato, Dino Araneo, Marco Cherubini, Nikolaus Muellner, Francesco S. D'Auria

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Mechanistic Modeling of Bearing Pad to Pressure Tube Contact Under Localized High Temperature Conditions in a CANDU Fuel

Farshad Talebi, John C. Luxat

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

Weimin Ma

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

Dan Quach, Paul Sermer, Fred Hoppe, Ovidiu Nainer, Bac Phan

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DRESDYN - A New Platform for Sodium Related Thermohydraulic Studies and Measurement Developments

Thomas Gundrum, Sven Eckert, Frank Stefani, Gunter Gerbeth

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

Hyungdae Kim, Jacopo Buongiorno

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Sensitivity and Uncertainty Analysis of Debris Bed Coolability

Sergey Yakush, Pavel Kudinov, Nazar Lubchenko

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

Brandon Wilson, Barton L. Smith

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Experimental Study on Influences of Kinematic Viscosity on Occurences of Cavitation Due to Sub-Surface Vortex

Toshiki Ezure, Nobuyuki Kimura, Jun Kobayashi, Hideki Kamide

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

Seth R. Cadell, Brian G. Woods

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MCCI Simulation Comparison Between MELCOR and CORQUENCH

Kevin Robb, Michael Corradini

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Extended Forward Sensitivity Analysis for Uncertainty Quantification

Haihua Zhao, Vincent A. Mousseau

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Modelling the Interaction of a Molten Seal and Solid Particles Using SPH and DEM Simulations: Application for a Passive New SCRAM System for LMR

Simon Vanmaercke, Gert Van Den Eynde, Engelbert Tijskens, Yann Bartosiewicz

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

Peter Hedberg, Hans Nilsson

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Melt Eruption Modeling for MCCI Simulations

Kevin Robb, Michael Corradini

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Experimental Study of Two-Phase Flows Under Reduced Gravity Conditions

Tirthankar Roy, Yang Liu, Shao-Wen Chen, Takashi Hibiki, Mamoru Ishii, Walter Duval

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Simulation of Water - Liquid Lead-Bismuth Eutectic Interaction Using Simmer-III Code

Shisheng Wang, Michael Flad, Werner Maschek, Andrei Rineiski

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

Alexander Gurevich, Ibrahim Abdalla, Armando Lopez

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Measurement of Film Dynamics in a Boiling Liquid Film

Shengjie Gong, Weimin Ma, Truc-Nam Dinh

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Analysis of Integral Circulation and Decay Heat Removal Experiments in the Lead-Bismuth CIRCE Facility with RELAP5 Code

Giacomino Bandini, Paride Meloni, Massimiliano Polidori, Pierantonio Gaggini, Mariano Tarantino, Andrea Ciampichetti

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Contactless Flowrate Sensors for NA, PBBI and PB Flows

Dominique Buchenau, Gunter Gerbeth, Janis Priede

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

Isaac Asher, Timothy Drzewiecki, Krzysztof Fidkowski, Thomas Downar

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

Despoina Chatzikyriakou, Jacopo Buongiorno, Djamel Lakehal

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

Van-Thai Nguyen, Byoung-Uhn Bae, Dong-Jin Euh, Chul-Hwa Song

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Simulation of Steam Bubble Transport in Primary System of Pool Type Lead Cooled Fast Reactors

Marti Jeltsov, Pavel Kudinov

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

Takahiro Arai, Masahiro Furuya, Taizo Kanai, Kenetsu Shirakawa

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Development of the Test Facilities for the Measurement of Core Flow and Pressure Distribution of SMART Reactor

Yungju Ko, Dong-Jin Euh, Youngjung Youn, In-Cheol Chu, Tae Soon Kwon

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

Noreddine Mesmous, Janusz Kowalski

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Subcooled Flow Boiling Experiment and Simulation for a Virtual Reactor

Masahiro Kawaji, Randy Samaroo, Joseph Kreynin, Taehun Lee, Sanjoy Banerjee

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

Mohan Yadav, Seungjin Kim

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

Abdelaziz Elmahdi, R. Roger, Michael E. Conner, Zeses Karoutas, Emilio Baglietto

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

Mohan Yadav, Ted Worosz, Seungjin Kim

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Steam Drum Level Dynamics in a Multiple Loop Natural Circulation System of a Pressure-Tube Type Boiling Water Reactor

Vikas Jain, Parimal Kulkarni, Arun Nayak, Pallippattu K. Vijayan, Dilip Saha, R. Sinha

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

Mohamed E. Shawkat, Hisham Hasanein, Yuksel Parlatan, Todd Daniels, Mohamed Bayoumi, Hassan AlBasha

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

Frederic Bertrand, Vincent Gatin, Fabrice Bentivoglio, Christine Gueneau

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

Saaransh Gulati, Jacopo Buongiorno, Djamel Lakehal

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Pool Boiling and Condensation Analysis for a Vertical Tube Bundle Condenser

Wenzhong Zhou, B. Wolf, Shripad Revankar

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

Ansheng Lin, Jong-Rong Wang, Yen-Shu Chen, Chunkuan Shih

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Coupled Nuclear-Thermalhydraulic Calculations for Fort St. Vrain Reactor

Benjamin R. Betzler, Eva E. Sunny, John C. Lee, William R. Martin

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Developments in Single Phase Fuel Assembly Simulations

Ferry Roelofs, Vinay R. Gopala, Dirk C. Visser, A. Shams, Jan-Aiso Nijeholt, Laltu Chandra

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Assessment of RELAP5/MOD3.3 Condensation Models for the Tube Bundle Condensation in the PCCS of ESBWR

Wenzhong Zhou, B. Wolf, Shripad Revankar

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Cyber-Security in a Nuclear Power Plant Simulator

M. Giersch, Nikolaus Muellner, Francesco S. D'Auria

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

Seungjin Kim, Justin Talley, Mohan Yadav, Andrew Ireland, Stephen M. Bajorek

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

Carla M. Xavier, Adriane P. Petry, Sergio V. Moller

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Regulatory Assessment of Effectiveness of ACR-1000 Emergency Core Cooling System

Aurelian Tanase, Robert Gibb, Aleksandar Delja

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

Kifah J. Takrouri, John C. Luxat, Mohamed S. Hamed

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

Yiqi Yu, Xu Cheng, Y.H. Yang

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Estimation of Flow-Induced Loads on a Down-Scaled Model of SMART Reactor Coolant System

Kyoung Rean Kim, Jin Seok Park, Won Jae Lee

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

Johannes Weis, A. Papukchiev, Martina Scheuerer

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The US NRC Advanced Gas Reactor Evaluator (AGREE)

Timothy Drzewiecki, Volkan Seker, Joseph Kelly, Thomas Downar

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

Hyung Gon Jin, Hee Cheon No, Young Soo Kim, Ho Sik Kim

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

Koichi Hata, Naoto Kai, Yasuyuki Shirai, Suguru Masuzaki, Akimichi Hamura

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Condensation in the Cold Leg As Results of ECC Water Injection During a LOCA: Modeling and Validation

Jun Liao, Cesare Frepoli, Katsuhiro Ohkawa

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

Thomas Frank, Florian Reiterer, Conxita Lifante

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The Development of a Realistic LOCA Evaluation Model Applicable to the Full Range of Breaks Sizes: Westinghouse Full Spectrum LOCA (FSLOCATM) Methodology

Cesare Frepoli, Katsuhiro Ohkawa

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

Cyril Baudry, Mathieu Guingo, Alexandre Douce, Jerome-Marcel Lavieville, Stephane Mimouni, Marc Boucker

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

Jorge Perez, Michael Bottcher, Victor H. Sanchez

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

Dimitrios Pavlidis, Danny Lathouwers

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

Luben Sabotinov

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Steam Condensation Induced Water Hammer Simulations and Measurements for Different Pipelines in Nuclear Reactor

Imre Barna, Gyorgy Ezsol

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WCOBRA/TRAC-TF2 Simulation of ROSA-IV/LSTF Natural Circulation Test ST-NC-02

Nikolay Petkov, Katsuhiro Ohkawa, Cesare Frepoli

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

Eckhard Krepper, Roland Rzehak

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CFD Application to PWR Subchannel Void Distribution Benchmark

Wang Ki In, Chang-Hwan Shin, Tae-Hyun Chun

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

Jean-Marie LeCorre, Carl Adamsson, Pablo Avarez

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A Discussion of Hyperbolicity in CATHENA 4: Virtual Mass and Phase-To-Interface Pressure Differences

Nusret U. Aydemir

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Best-Estimate LOCA Analysis over the Full Spectrum of Postulated Breaks Using Westinghouse FULL SPECTRUMTM LOCA Methodology

Michael Shockling, Cesare Frepoli, Katsuhiro Ohkawa

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

Gerardo M. Grandi, Sten-Örjan Lindahl

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Computational Models to Determine Fluiddynamical Transients Due to Condensation Induced Water Hammer (CIWH)

Harald Swidersky, Andreas Schaffrath, Andreas Dudlik

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Horizontal Stratified Flow Model for the 1-D Module of WCOBRA/TRAC-TF2: Modeling and Validation

Jun Liao, Cesare Frepoli, Katsuhiro Ohkawa

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

Hisham Hasanein, Yuksel Parlatan, Ab Tahir, Sun John, Jose Torres, Michael Kisil

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Properties of Flooding Wave in Vertical Churn Flow

Ke Wang, Bofeng Bai, Bo Yang, Chen Xie

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Tripartite Mass Transfer Model: Development, Implementation in DYVRO, Verification and Validation

Thorsten Neuhaus, Andreas Schaffrath

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Experimental Investigation of Nucleate Boiling on Heated Surfaces Under Sub Cooled Conditions

Clemens Schneider, R. Hampel, A. Traichel, A. Hurtado, S. Meissner, E. Koch

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

Tomio Okawa, Yosuke Yamagoe, Rouhollah Ahmadi

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

Jil Gueguen, Fabrice Francois, Herve Lemonnier

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Delayed Equilibrium Model and Validation Experiments for Two-Phase Choked Flows Relevant to LOCA

Yann Bartosiewicz, Jean Seynhaeve, Guillaume Serre

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Flow Boiling Critical Heat Flux Enhancement by Using Magnetic Fluids and External Magnetic Fields

Taeseung Lee, Yong Hoon Jeong

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

Matteo Bucci, Walter Ambrosini, Nicola Forgione, Francesco Oriolo, Sandro Paci

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

Ezequiel Manavela Chiapero, Maria Fernandino, Carlos Dorao

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Generalized Quazi-One-Dimensional Model of Non-Homogeneous Two-Phase Flow and Criterion for Density Wave Oscillation in Parallel Channels With Riser

Yuri Kornienko

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Experimental Study on the Pool Boiling CHF Enhancement Using Magnetic Fluid

Jong Hyuk Lee, Yong Hoon Jeong

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

Matteo Bucci, Walter Ambrosini, Nicola Forgione, Donato Lioce

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Application of Ant Colony Optimization Approach to Severe Accident Management Measures of Maanshan Nuclear Power Plant

Chih-Ming Tsai, Shih-Jen Wang

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Analysis of Boiling

Nikolay Ivanov Kolev

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

Hideki Tamura, Yusuke Ozaki, Nobuyuki Takenaka, Koji Miyishi, Akira Nakamura

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Droplet Entrainment Rate in Vertical Annlar Two-Phase Flow

Pravin Sawant, Yang Liu, Mamoru Ishii, Mori Michitsugu

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

Xia Wang, Xiaodong Sun, Ben Doup, Haihua Zhao

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Flow Boiling Critical Heat Flux Enhancement on the 2-D Slice for Boric Acid and TSP Solution

Hae Min Park, Sun Heo, Chanyi Song, Yong Hoon Jeong

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A CFD Benchmarking Exercise Based on Flow Mixing in a T-Junction

Brian L. Smith, John H. Mahaffy, Kristian Angele

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Bubble Dynamics in Single Component Fluid

Nikolay Ivanov Kolev

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Experimental Investigation Into the Effects of Reactor Coolant Additives on Boiling Phenomena in Pressurized Water Reactors

Richard Nakath, Christoph Schuster, Antonio Hurtado

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

Laurent Bricteux, Matthieu Duponcheel, Gregoire Winckelmans, Yann Bartosiewicz

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Numerical Predictions of Bubbly Two-Phase Flows with Openfoam

Edouard Michta, Kai Fu, Henryk Anglart, Kristian Angele

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Analysis of Two Phase Natural Circulation Flow in the Reactor Cavity Under External Reactor Vessel Cooling

Rae-Joon Park, Kwang Soon Ha, Sang Baik Kim, Seong Wan Hong, Sun Seo

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

A. Vaidya, N.K. Maheshwari, Pallippattu K. Vijayan, D. Saha

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Study on In-Vessel Retention (IVR) Strategy for CPR1000

Xing Chen, Huiyong Zhang, Juanhua Zhang, Shishun Zhang, Jiming Lin

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Analyses of Large Scale Tests Addressing the Performance of a Containment Cooler and Its Effect on Gas Distribution

Michele Andreani, Guillaume Mignot

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

Ivan Otic, Xu Cheng

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

Maria Jaromin, Henryk Anglart

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Physics of Coolability of Top Flooded Molten Corium

Parimal Kulkarni, Raj Singh, Arun Nayak, Pallippattu K. Vijayan, Dilip Saha, R. Sinha

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Modeling of Time-Averaged Film Thickness Distribution Downstream of BWR Functional Spacers

Manuel Damsohn, Horst-Michael Prasser

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

Iztok Tiselj

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Large Eddy Simulations of Turbulent Flows at Supercritical Pressure

Claus Kunik, Ivan Otic, Thomas Schulenberg

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Prediction of Boiling-Induced Natural Circulation Flow in an Inclined Channel with Non-Uniform Flow Area

Kwang Soon Ha, Fan-Bill Cheung, JinHo Song, Rae-Joon Park, Sang Baik Kim

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Spray Model Validation on Single Droplet Heat and Mass Transfer for Containment Applications - SARNET-2 Benchmark

Jeanne Malet, Arne Siccama, Sandro Paci, Zbynek Parduba, Lubica Kubisova, Mantas Povilaitis, Zhanjie Xu, Walter Klein-Hessling, Siegfried Arndt, Giovanni Manzini, Stephane Mimouni, Thomas Gelain, Marek Stempniewicz

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Modeling the Turbulent Heat Fluxes in Low Prandtl Number Shear Flows

Thomas Baumann, Andre Loges, Luca Marocco, Torsten Schenkel, Thomas Wetzel, Robert Stieglitz

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

Morena Angelucci, Walter Ambrosini, Nicola Forgione

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INKA Large Scale Thermohydraulic Test Facility

Stephan Leyer, Michael Wich

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Computer Codes Validation for Conditions of Core Voiding

Aleksandar Delja, Pat Hawley

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

Katrien VanTichelen, Matthias Vanderhaegen, Santhosh Jayarayu, Steven Keijers, Ferry Roelofs

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Measurement of Two-Phase Flow Parameters with Multi-Channel Gamma Densitometry and Local Void Probes at the INKA Test Facility

Eckhard Schleicher, Andre Bieberle, Martin Tschofen, Uwe Hampel, Natalia Lineva, Fabian Maisberger, Stephan Leyer

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BETHSY 6.2TC Test Calculation with TRACE and RELAP5 Computer Code

Andrej Prosek, Ovidiu-Adrian Berar

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

Andre Loges, Thomas Baumann, Luca Marocco, Thomas Wetzel, Robert Stieglitz

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

Eugenio Molfese, Walter Ambrosini, Nicola Forgione, Pallippattu K. Vijayan, Manish Sharma

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

Hussam Zahlan, Dionysius Groeneveld, Stavros Tavoularis

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Analysis of the Performance of the KERENA Emergency Condenser

Annalisa Manera, Horst-Michael Prasser, Stephan Leyer

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TRACE Assessment of the ACHILLES ISP-25 Reflood Transient

Boyan Neykov, Vesselin Palazov, Thomas Downar, Kostadin Ivanov

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

Carl Adamsson, Jean-Marie LeCorre

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Testing Special TRACE5 Models Applied to SBLOCA Scenarios

Sergio Gallardo, Gumersindo Verdu, Andrea Querol

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

Pierre Peturaud, Robert Salko, Andre Bergeron, Suresh Yagnik, Maria Avramova

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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, Georg Lerchl, Johannes Weis, Martina Scheuerer, Henrique Austregesilo

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MINIPANDA - A Small Scale Containment Test Facility with Novel Instrumentation Is Used for Code Validation for an Air Ingress Scenario

Martin Ritterath, Johannes Baggermann, Stephan Kelm, Onur Ozturk, Horst-Michael Prasser

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Advanced ATHLET Model for the UPTF Facility

Sergey Nikonov, Ihor Pasichnyk, Kiril Velkov

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Containment Scaling: Experimental Investigation of the Breakup of a Stratified Layer Due to a Vertical Jet from Below on Two Scales

Martin Ritterath, Raphael Heierli, Guillaume Mignot, Horst-Michael Prasser

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Assessment of Interfacial Drag and Two Phase Pressure Drop Models of TRACE Code

Subash Sharma, Xiaohong Yang, Takashi Hibiki, Mamoru Ishii

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

Belgacem Hizoum, Pradip Saha, Jens G.M. Andersen, Kristin Whitlow

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

Douglas Miller, Fan-Bill Cheung, Stephen M. Bajorek

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Validation of Post-Dryout Phenomena for the Space Code

Kyung Doo Kim, S.K. Moon, B.J. Kim, S.W. Lee

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Correlation Between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice

Yoichi Utanohara, Akira Nakamura, Yukinori Nagaya, Michio Murase

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Simulate-3K Linkage with Reactor Systems Codes

Jerry Judd, Gerardo M. Grandi

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

Ulf Schittek, Marco K. Koch

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Experimental Study on Penetration Length in a Small Size Branch Pipes in Nuclear Power Plant

Takahiro Iguchi, Atsushi Saito, Nobuyuki Takenaka, Koji Miyishi, Akira Nakamura

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CFD-Neutronic Coupled Calculation of a Quarter of a Simplified PWR Fuel Assembly Using ANSYS CFX 12.1 and PARCS

Carlos Pena Monferrer, Filippo Pellacani, Sergio Chiva Vicent, Teresa Barrachina, Rafael Miro, Rafael Macian-Juan

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Heat Flux and Temperature Determination on the Control Rod Outer Surface

Jan Taler, Artur Cebula, Jerzy Marcinkiewicz, Hernan Tinoco

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

Holger Nowack, Walter Erdmann, Nils Reinke

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Large-Eddy Simulation of Thermal Mixing in a T-Junction With Conjugate Heat Transfer

David Kloeren, Eckart Laurien

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Revisiting Temporal Accuracy in Neutronics/T-H Code Coupling Using the NURESIM LWR Simulation Platform

Omar Zerkak, Ivan Gajev, Annalisa Manera, Tomasz Kozlowski, Andre Gommlich, Stephanie Zimmer, Soren Kliem, Nicolas Crouzet, Martin A. Zimmermann

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

Tadakatsu Yodo, Yusuke Sato, Takanori Yumura, Yasushi Makino, Takayuki Suemura

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Stratification Criterion for the CATHARE Code

Guillaume Serre, Dominique Bestion, Maxime Franco, Manon Bottin, Muriel Marchand

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Suppression and Control of Thermal Fatigue by an Active Flow Control Magnet (AFCOM)

Kazuhisa Yuki, H. Yamano

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A Multi-Physics Code System Based on ANC9, VIPRE-W and BOA for CIPS Evaluation

Baocheng Zhang, Jeffery Secker, Charles Beard, Peter Hilton, Guoqiang Wang, Robert Oelrich, Zeses Karoutas, Yixing Sung

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

Shane Park, Hyun S. Park, Gyoodong Jeun, Beom J. Cho

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Simulation of Bundle Test Quench-12 With Integral Code MELCOR

Jiri Duspiva

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Experiments on Main Steam Line Break in the Test Facilities PKL and ROCOM

Klaus Umminger, Lars Dennhardt, Soren Kliem

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Simulation of a Simple RCCS Experiment with RELAP5-3D System Code and Computational Fluid Dynamics Computer Program

Rodolfo Vaghetto, Hong Wei, Yassin A. Hassan

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

Stephan Kelm, Ernst-Arndt Reinecke, Wilfried Jahn, Hans-Josef Allelein

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Large-Eddy Simulation of a Single-Phase Pressurized Thermal Shock

M.S Loginov, A. Shams, E.M.J Komen, T. Hoehne

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PAR Elevation Influence on Hydrogen Floor Layer Depth

Frederic Dabbene

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

Guillaume Mignot, Ralf Kapulla, Nejdet Erkan, Robert Zboray, Domenico Paladino

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

Thorsten Hollands, Christine Bals, Henrique Austregesilo, Wolfgang Luther

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

Roberta C. Hansson, Louis T. Manickam, Truc-Nam Dinh

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Experimental Studies on Heat Transfer in External Cooling of the Reactor Pressure Vessel

Timo Merisaari, Antti Rasanen, Antti Rasanen, Riitta Kyrki-Rajamaki, Karoliina Myllymaki, Timo Toppila

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Scaling of a PWR Steam Generator Simulator with the Help of CFD

Abdelouahab Dehbi, Hassan Badreddine

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

Marco Gartner, Cameron Tropea, Suad Jakirlic, Sanjeev Gupta

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Investigation on the Influence of Pressure and Temperature on the Ignition Limits of Hydrogen Inside Recombiners

Nicolas Meynet, Stefan Engelhardt, Ahmed Bentaib

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

Frank Barthel, Dietrich Hoppe, Lutz Szalinski, Uwe Hampel

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Modelling of Solidification Effect in Eulerian Fuel-Coolant Interaction Codes

Mitja Ursic, Matjaz Leskovar

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Fracture Mechanics Analysis on VVER1000 RPV with Different Methodologies

Giuseppe Agresta, Dino Araneo, Francesco S. D'Auria

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

Kil-Mo Koo, Seung-Tae Lee, Chul-Hwa Song

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Experimental Investigation and Modelling of Bulk Boiling for CFD Application

Josip Kutnjak, Rudi Kulenovic, Eckart Laurien

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Study on the Transient and Stability Behaviour of a Boiling Two-Phase Natural Circulation Loop With Al2O3 Nanofluids

Arun Nayak, Parimal Kulkarni, Pallippattu K. Vijayan

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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, Marc Guetg, John Kickhofel, Frank Barthel, Uwe Sprewitz, Uwe Hampel, Horst-Michael Prasser

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Thermal Design Aspects of High-Efficiency Channel for SCWRs

Wargha Peiman, Igor Pioro, Kamiel Gabriel

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Integrated Particle Imaging Velocimetry and Infrared Thermometry for High Resolution Measurement of Subcooled Nucleate Pool Boiling

Xili Duan, Jacopo Buongiorno, Thomas McKrell

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Natural Circulation Flow Behavior at Reduced Inventory Conditions

Parimal Kulkarni, Arun Nayak, Pallippattu K. Vijayan, Dilip Saha

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

Jan Taler, Bohdan Weglowski, Tomasz Sobota, Magdalena Jaremkiewicz, Dawid Taler

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

Krysten King, Shona Draper, Wargha Peiman, Ayman Abdalla, Arif Qureshi, Jon P. Joel, Igor Pioro, Kamiel Gabriel

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Observation of High Heat Flux Boiling Structures in a Horizontal Pool by a Total Reflection Technique

In-Cheol Chu, Hee Cheon No, Chul-Hwa Song

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Thermosiphon Circulation Inside Vertical Condenser Bundle with Through Flow

Kareem Aly, Nick Idvorian

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Liquid Film Thickness of Individual Bubbles in a Narrow Channel

Daisuke Ito, Horst-Michael Prasser, Masanori Aritomi

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

Graham Richards, A.S. Shelegov, P.L. Kirillov, Igor Pioro, Glenn Harvel

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A Simultaneous Observation of Bubble Growth and Microlayer Behavior for an Isolated Boiling Regime of Saturated Water

In-Cheol Chu, Chul-Hwa Song, Hee Cheon No

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Numerical Simulations of Upper Plenum Thermalhydraulics of Monju Reactor Vessel Using High Resolution Mesh Models

Hiroaki Ohira, Kei Honda, Masutake Sotsu

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

Ossama Merroun, Jean-Yves Malo, Philippe Guimbal, Christian Gonnier, Damien Fourmentel, Jean-Pierre Chauvin, Gilles Bignan, Jacques Andre, Yves Zerega, Aurika Janulyte, Michel Carette, Julie Brun, Abdallah Lyoussi, Christelle Raynaud-Carette, Jean-François Villard

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Improvement of Image Processing Algorithms for Annular Flow

Wesley Kokomoor, DuWayne Schubring

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Benchmark Analyses of Sodium Convection in Upper Plenum of the MONJU Reactor Vessel - Comparison Between Plant System Analysis Code CERES and CFD Code

Yoshihisa Nishi, Nobuyuki Ueda, Shinji Yoshikawa, Akira Miyakawa, Mitsuya Kato

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

Manuel Damsohn, Horst-Michael Prasser

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

Andrew Lukomski, Kamiel Gabriel, Igor Pioro

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Options and Challenges of Steam Cycle Components for SCWR

Thomas Schulenberg, Marc Schlagenhaufer, Heiko Herbell

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Interfacial Area Transport of Steam-Water Two-Phase Flow in a Vertical Annulus at Elevated Pressures During Sub-Cooled Boiling

Basar Ozar, Caleb Brooks, Takashi Hibiki, Mamoru Ishii

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Analysis of Thermal Stratification in the Upper Plenum of the "Monju" Reactor Vessel - Effect Of Chamfer Of Flow-Hole On Thermal Stratification -

Hiroyasu Mochizuki, M. Takano, Masahito Takano

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

Gerry Frappier, Alexandre Viktorov

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Trio_U Analysis of Natural Convection in the Upper Plenum of the MONJU Reactor

Ulrich Bieder, Gauthier Fauchet, Shinji Yoshikawa

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

Walter Villanueva, Chi-Thanh Tran, Pavel Kudinov

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

Minoru Yamada, Hiroichi Nagumo, Ikuo Kinoshita

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Basic Equations of Interfacial Area Transport in Gas-Liquid Two-Phase Flow

Isao Kataoka, Kenji Yoshida, Masanori Naitoh, Hidetoshi Okada, Tadashi Morii

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

Kenichiro Nozaki, Akitoshi Hotta, Shinya Kosaka, Shoichi Suehiro, Daisuke Fujiwara, Shinya Mizokami

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Interfacial Area Transport Equation Evaluation Methodology in Large Diameter Pipes

Joshua Schlegel, Shuichiro Miwa, Shao-Wen Chen, Takashi Hibiki, Mamoru Ishii

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Numerical Analysis of Thermal Stratification in the Reactor Upper Plenum of MONJU with 1/3 Sector and Full Sector Models

Makoto Shibahara, Takashi Takata, Akira Yamaguchi

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

Walter Villanueva, Chi-Thanh Tran, Pavel Kudinov

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

Soren Alt, M. Holker, Wolfgang Hoffmann, Wolfgang Kaestner, Holger Kryk, Stefan Renger, Andre Seeliger

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

Carl Adamsson, Jean-Marie LeCorre

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Interfacial Area Transport in Two-Phase Flows in a Scaled 8X8 Rod Bundle Geometry at Elevated Pressures

Xiaohong Yang, Joshua Schlegel, Sidharth Paranjape, Yang Liu, Shao-Wen Chen, Takashi Hibiki, Mamoru Ishii

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Analysis of Thermal Stratification in the Upper Plenum of the "Monju" Reactor Vessel

Tanju Sofu, Justin W. Thomas

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

Daniel J. Pohl, Jason Pascoe, Adrian I. Popescu

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Coupled Lagrangian and Eulerian Simulation of Bubbly Flows in Vertical Pipes : Validation with Experimental Data

Jose Luis Munoz-Cobo, Sergio Chiva, Mohamed Ali Abd El Aziz Essa, Santos Mendes

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Main Results of the OECD Best Estimate Methods, Uncertainty and Sensitivity Evaluation (BEMUSE) Programme

Horst Glaeser, Francesco S. D'Auria, Agnes DeCrecy, Francesc Reventos

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

Philippe Fillion, Matteo Bucci

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Investigation of the Uncertainty of Governing Equation Systems in Thermalhydraulic Calculation

Tomasz Skorek, Bernhard Krzykacz-Hausmann, Henrique Austregesilo

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Fuel Assembly Simulations Using LRGR-CFD and CGCFD

Ferry Roelofs, Vinay R. Gopala, Laltu Chandra, Mathias Viellieber, Andreas Class

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Uncertainty and Sensitivity Analysis for a Nuclear Power Plant Large Break Loss of Coolant Accident (LB-LOCA) in the Context of OECD BEMUSE Programme

Francesc Reventos, Horst Glaeser, Francesco S. D'Auria, Agnes DeCrecy

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

Maria Avramova, Alexander Velazquez-Lozada, Adam Rubin

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

Alessandro Petruzzi, Francesco S. D'Auria, Nikolaus Muellner, Oscar Mazzantini

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Perspectives in the Simulation of PTS Scenarios: Form RANS to V-LES & LES and from Phase-averaged to Interface Tracking Methods

Djamel Lakehal, M. Labois, C. Narayanan

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Effectiveness of Core Exit Thermocouple (CET) Temperature Indication in Accident Management of Light Water Reactors

Hideo Nakamura, Artur Muhleisen, Francesco S. D'Auria, Nikolaus Muellner, Jose Ramon Alonso, Robert Prior, Joerg Dreier, Klaus Umminger, Oddbjorn Sandervag, Ivan Toth, Abdallah Amri

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

Tae-Wan Kim, Annalisa Manera

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A Simple Model for Two-Phase Slug Flow Induced Damping

Njuki Mureithi, Teguewinde Pierre Sawadogo, Fabien Bernard

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Algebraic Turbulent Heat Flux Model for Prediction of Thermal Stratification in Piping System

Marco Pellegrini, Hiroshi Endo, Elia Merzari, Hisashi Ninokata

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Solution of the International Benchmark with Trip of One of Four Reactor Coolant Pumps for VVER-1000 Reactor Plants Using the Computer Code Package KORSAR/GP

Ivan Petkevich, Grigory Alekhin, Mikhail Bykov

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VIPRE-W Benchmark With PSBT Void and Temperature Test Data

Yixing Sung, Robert Oelrich, Charles C. Lee, Nicolas Ruiz-Esquide, Marcelo Gambetta, Claudio Mazufri

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CFD Simulations of a Turbulent Flow in a T-Junction

Tadashi Morii, Yoichi Ohnishi, Karin Hirakawa, Akira Nakamura

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Validation of STAR-CCM+ for Buoyancy Driven Mixing in a PWR Reactor Pressure Vessel

Victor Petrov, Annalisa Manera

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Void Fraction Prediction of NUPEC PSBT Tests by CATHARE Code

Alessandro DelNevo, Lorenzo Michelotti, Francesco S. D'Auria, F. Moretti, D. Rozzia

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

Xuan Zhang, Shudong Yu

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

Atef Mohany, Marwan Hassan

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Development of a Three-Dimensional Momentum Source Model for Wire-Wrapped Rod Bundles

Rui Hu, Thomas H. Fanning

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CFD Simulations of Buoyancy Driven Flow Mixing Experiments Performed at the ROCOM Facility

Guillaume Pochet, Xingyuan Zhang, Didier Leonard

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

Hisashi Ninokata, Hideki Kamide

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Numerical Simulations of Developing Flow and Vortex Street in a Rectangular Channel with a Cylindrical Core

Dongil Chang, Stavros Tavoularis

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

Hee Cheon No

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

Marwan Hassan, Atef Mohany

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RELAP5 Analysis of Two-Phase Decompression and Rarefaction Wave Propagation Under a Temperature Gradient

Nathan Lafferty, Victor H. Ransom, Martin Lopez de Bertodano

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Unsteady Hydraulic Characteristics in Pipe with Elbow Under High Reynolds Condition

Ayako Ono, Nobuyuki Kimura, Hideki Kamide, Akira Tobita

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Slug Modeling with 1D Two-Fluid Model

Iztok Tiselj

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Simulation of Laminar Pulsations in a Rectangular Duct Containing a Rod

Alan Chettle, Marilyn Lightstone, Stephen Tullis

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Supercritical Flow and Heat Transfer in Advanced Reactors

Michael Corradini

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

Alexandre V. dePaula, Sergio V. Moller

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Pressure Surge in Wendelstein 7-X Experimental Stellarator Facility

Tadas Kaliatka, Eugenijus Uspuras, Algirdas Kaliatka

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An Experimental Study on the Identification of Flow Patterns Responsible for Crossflow in a Vertical Tube Bundle Geometry

Amer Mahmood, Martin Rohde, Tim H.J.J. vander Hagen, Rob F. Mudde, Tsutomu Ikeno

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Thermalhydraulics and Safety Concepts of Supercritical Water Cooled Reactors

Thomas Schulenberg, Dirk C. Visser

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

Michio Murase, Ikuo Kinoshita, Chihiro Yanagi, Y. Utanohara, Takashi Takata, Akira Yamaguchi, Akio Tomiyama

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Check Valve Slam Caused by Air Intrusion in Emergency Cooling Water System

C. Samuel Martin

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Numerical Simulation of the Flow in a Tight Lattice SFR Rod-Bundle with Grid Spacers

Elia Merzari, Paul Fischer, William D. Pointer, Hisashi Ninokata

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

Horst-Michael Prasser

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

Isabelle Dor, Philippe Germain

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Condensation-Induced Water Hammer - Overview and Own Experiments

Stefan Dirndorfer, Michael Dorfler, Helmut Kulisch, Andreas Malcherek

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Analyses of Light Gas Stratification Erosion and Break-Up Under the Effect of a Vertical Jet: CFD Simulations for a Common Test in the PANDA and MISTRA Facilities

Medhat Sharabi, Michele Andreani

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Thermalhydraulic Analysis of Spent Fuel Baskets

Jake Xu, Khairy Khair, Ralph Granz, Amarjit Banwatt

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And Now for Something Completely Different: Condensation Induced Water Hammer and Steam Assisted Gravity Drainage in the Athabasca Oil Sands

Mike R. Carlson

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Numerical Assessment of PANDA Experiments Covering Steam/Air/Helium Mixtures

Namane Mechitoua, Stephane Mimouni

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

Kyoungwoo Seo, Young-Chul Park, Dae-Young Chi, Juhyeon Yoon

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

Simon Lo, Andrew Splawski, Byong Jo Yun

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

Gregory M. Cartland Glover, Holger Kryk, Wolfgang Kaestner, Soren Alt, Frank Zacharias, Andre Seeliger, Stefan Renger, Eckhard Krepper, Alexander Kratzsch, Frank-Peter Weiss

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Challenges Associated to the Mitigation of ULOF in Sodium-Cooled Fast Reactor Cores

Gerald Rimpault, Sandra Poumerouly, Johann Lecerf

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Simulation of LOCA within a German BWR Containment with the Coupled Version of ATHLET-COCOSYS

Mathias Hoffmann, Ulf Schittek, Uwe Gall, Marco K. Koch

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

Masahito Takano, Hiroyasu Mochizuki

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Aerosol Removal by Emergency Spray in PWR Containment: Synthesis of the TOSQAN Aerosol Tests

Emmanuel Porcheron, Pascal Lemaitre, Denis Marchand

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

Humberto Soares, Ivan Dionysio Aronne, Ygor Henrique deAlmeida, Claubia Pereira, Antonella Lombardi Costa, Claubia Pereira, Maria Auxiliadora Fortini Veloso

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

Hyoung Kyu Cho, Byong Jo Yun, Jae Ryong Lee, Han Young Yoon, Jae Jun Jeong

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Study on Containment Overpressure Fragility Curve and Ultimate Load for CPR1000

Chen Peng, Jiming Lin, Shishun Zhang, Jiliang Sun

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

Jeanne Malet, Thomas Gelain, Olivier Degrees du Lou, Virginie Daru

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CFD Modelling of Sodium Spray Combustion

Pratap Sathiah, Arne Siccama, Ferry Roelofs

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TRACE Code Validation for DVI Line Break LOCA in the ATLAS Facility

Fabio Veronese, Tomasz Kozlowski

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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

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Thermally Stratified Sodium Channel Flow: Turbulence and Modelization

Marco Pellegrini, Hiroshi Endo, Hisashi Ninokata

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

Wadim Jaeger, Victor H. Sanchez

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Laminar Flame Proprieties and Flame Acceleration Prediction of Hydrogen-Methane Mixtures

Kodjo Coudoro, Nabiha Chaumeix, Ahmed Bentaib, Claude Paillard

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Qualification of TRACE V5 Code Against Fast Cooldown Transient in the PKL-III Integral Test Facility

Eugenio Coscarelli, Alessandro DelNevo, Francesco S. D'Auria

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

Jordi Freixa, Davide Bertolotto, Annalisa Manera

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Modeling of Compartment Fire

Pratap Sathiah, Arne Siccama, Dirk C. Visser, Ed Komen

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TRACE Validation Against Fix-II Test No. 3025

Lukasz Sokolowski, Tomasz Kozlowski

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

Chi Thanh Tran, Pavel Kudinov

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

Konstantin Nikitin, Annalisa Manera, Hakim Ferroukhi, Jerry Judd, Gerardo M. Grandi

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Simulation of THAI HD-12 and HD-22 With the Flame Front Model of ASTEC Using Different Correlations for the Turbulent Burning Velocity

Thimo Brahler, Hermann-Josef Wagner, Marco K. Koch

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Analisis of Surge Line MBLOCA Sequences With HPSI Failed

Cesar Queral, Juan Gonzalez-Cadelo, David Prada, Javier Montero, Juan Martinez-Murillo, Julio Perez

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CFD Analysis of Heat Transfer in Low Prandtl Number Fluid Flows

A. Borgohain, N.K. Maheshwari, Pallippattu K. Vijayan, R.K. Sinha

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MARS-KS Assessment of TRACE Fundamental Problems

Won Joon Chang, D.-H. Yoon, N. Kim, S. Ahn, B. Shin, S. Ahn

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Experimental and MARS Code Simulations of DVI Line 25% and 50% Break LOCAs using SNUF for APR1400

Xinguo Yu, Keohyoung Lee, Goon-Cherl Park

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The Development and Assessment of TRACE Model for Maanshan PWR

Hao-Tzu Lin, Jong-Rong Wang, Jung-Hua Yang, Chunkuan Shih

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An Approach to Validation of Coupled CFD and System Thermalhydraulics Codes

Marti Jeltsov, Francesco Cadinu, Walter Villanueva, Aram Karbojian, Kaspar Kööp, Pavel Kudinov

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

Benjamin Collins, Linsen Li, Shane Stimpson, Daniel Jabaay, Andrew Ward, Yunlin Xu, Thomas Downar, Dean Wang

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An Integral Effect Test on the Feedwater Line Break of the APR1400 with the ATLAS Facility

Hyun-Sik Park, Seok Cho, Kyoung-Ho Kang, Yeon-Sik Kim, Ki-Yong Choi

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Coupled DNS/RANS Simulation of Fission Gas Discharge During Loss-of-Flow Accident in Gen-IV Sodium Fast Reactor

Igor Bolotnov, Farhad Behafarid, Dillon Shaver, Steven Antal, Ken Jansen, Michael Podowski

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

Roman Thiele, Weimin Ma, Henryk Anglart

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Hydraulic Benchmark Data for PWR Mixing Vane Grid

Michael E. Conner, Elvis E. Dominguez-Ontiveros, Yassin A. Hassan

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Integration of CFD Into Systems Analysis Codes for Modeling Thermal Stratification During SFR Transients

Thomas H. Fanning, Justin W. Thomas

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Modelling and Validation of Turbulent Boiling Flow in a Rectangular Channel

Bostjan Koncar, Marko Matkovic, A. Prosek

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Experimental Investigation of Air Bubble Flows in a Water Pool

Benjamin Balewski, Sanjeev Gupta, Karsten Fischer, Gerhard Poss

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

Kenichi Katono, Toshiki Matsubayashi, Koji Nishida, Akio Tomiyama

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Benchmark Testing the ODEN CHF Loop to Columbia University HTRF

L. David Smith, Anders Hallehn, Abdelaziz Elmahdi, Dong-Yuan Sheng, Henrik Tejne

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Thermalhydraulics and Neutronics Studies on the FP7 CP-ESFR Oxide and Carbide Cores

Luca Ammirabile, Haileyesus Tsige-Tamirat

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

Hyoung Tae Kim, Bo-Wook Rhee, Joo Hwan Park

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Application of Vector Finite Volume Method for Electromagnetic Flow Simulation

Takashi Takata, Ryoji Murashige, Toshinori Matsumoto, Akira Yamaguchi

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

Takanori Yumura, Tadakatsu Yodo, Yasushi Makino, Takayuki Suemura

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Reproducibility of Heat Transfer Tests in a 5X5 Bundle Geometry

Geraud Cubizolles, Philippe Clement, Dionysius Groeneveld

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Design and Performance Verification of Fuel Assembly and Steam Generator Simulators for SMART Reactor

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The Stability Analysis of LAPUR6 for Chinshan BWR Nuclear Power Plant

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Modeling of the PACTEL Facility and Simulation of a Small Break LOCA Experiment With the TRACE V5.0 Code

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

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Leonardo C. Ruspini, Carlos Dorao, Maria Fernandino

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Experimental Study of Undeveloped Nucleate Boiling on the Horizontal Tube Heated by Condensing Steam

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

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

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Water Test of Natural Circulation for Decay Heat Removal in JSFR

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Mixing Process by Molecular Diffusion and Natural Circulation of Two Component Gases in a Reverse U-Shaped Channel

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Determination of Mixing Factors for VVER-440 Fuel Assembly Head

Sandor Toth, Attila Aszodi

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

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Sodium Experiment on Fully Natural Circulation Systems for Decay Heat Removal in Japan Sodium-Cooled Fast Reactor

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Interaction Effects Between Laminar Natural Convection and Surface Thermal Radiation in PHWR Reactor Channels

Deepthi Chandramouli, Murugesan Rajendrakumar, K. Velusamy, P. Chellapandi

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

Xiaoyang Gaus-Liu, Alexei Miassoedov, Jerzy Foit, Thomas Cron, Frank Kretzschmar, Thomas Wenz, Silke Schmidt-Stiefel

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Development of Core Hot Spot Evaluation Method for Natural Circulation Decay Heat Removal in Sodium Cooled Fast Reactor

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Computational Fluid Dynamic Investigations of Thermal Stratification in the Hot Pool of MONJU Reactor and Comparison with Measured Data

Juby Abraham, K. Velusamy, P. Chellapandi

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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, Marina Perez, Francesc Reventos, C. Allison

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Numerical Simulations of the TOPFLOW-PTS Steam-Water Experiment

Pavel Apanasevich, Dirk Lucas, Thomas Hoehne

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Interaction of a Helium/Air Stratified Layer with an Air Jet Coming from Below: Large and Small Scale Experiments and Scaling Analysis

Jerome Brinster, Etienne Studer, Isabelle Tkatschenko, Danielle Abdo

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DNS for Multiphase Flow Model Generation and Validation

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

Jun Yang, Sung Choi, Jaehyok Lim, Doo Lee, Somboon Rassame, Takashi Hibiki, Mamoru Ishii

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TOPFLOW-PTS Air-Water Experiments on the Phase Separation in the ECC Nozzle and the ECC Water Mixing During PTS Scenarios

Tobias Seidel, Matthias Beyer, Uwe Hampel, Dirk Lucas

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