ICAPP 2007

2007 International Congress on Advances in Nuclear Power Plants

“The Nuclear Renaissance at Work”

May 13-18, 2007 • Nice Acropolis, France

Home Organizers Call For Papers Papers/Program Highlights/Plenary Nice/Hotels Exhibition Registration

 

Technical Program

ICAPP Topical Areas

  

Authors and Organizers of ICAPP, please note the following abbreviations which indicate the status/progress of the abstracts and papers:


Abs.r = Abstract received awaiting review.
Abs.a = Abstract approved.
Draft = Draft received - sent for review.
Revd. = Draft reviewed.
Final = Final paper received.
Cdrom = All materials received (electronic paper and copyright information...) at ICAPP office and final paper sent to CD Publication.
Key.n = Keynote paper.

0.00: Unassigned Abstracts/Papers

1.00: Water-Cooled Reactor Programs and Issues

2.00: High Temperature Gas Cooled Reactors

3.00: LMFR & Longer Term Reactor Programs

4.00: Operation, Performance & Reliability Management

5.00: Plant Safety Assessment and Regulatory Issues

6.00: Thermal Hydraulic Analysis and Testing

7.00: Fuel Cycle and Waste Management

8.00: Materials and Structural Issues

9.00: Nuclear Energy and Sustainability

10.00: Near Term Deployment Context Issues

11.00: Reactor Physics and Analysis

12.00: Innovative and Space Reactor Systems
13.00: Plenary Sessions

14.00: Key Note Sessions

 

Up

0.00: Unassigned Abstracts/Papers

Up

1.00: Water-Cooled Reactor Programs and Issues
Bernard Debontride, AREVA NP; Tour Areva , 92084 Paris-la-Défense ; , France; Ph: 33 1 47 96 17 64 FAX: E-mail:bernard.debontride@areva.com
Richard Swinburn, Rolls-Royce; Rolls-Royce plc, PO Box 2000 ; Derby, DE21 7XX United Kingdom; Ph: 44 (0)1332 632174 FAX: E-mail:Richard.Swinburn@rolls-royce.com
Takashi Kanagawa, Mitsubishi Heavy Industries; Mitsubishi Heavy Industries, Ltd., Nuclear Systems Engineering Dept. 3-1, Minatomirai 3-chome, Nishi-ku; Yokohama , Kanagawa-pref. 220-8401 Japan; Ph: 81-3-6716-4960 FAX: 81-3-6716-5844 E-mail:takashi_kanagawa@mhi.co.jp
Hideaki Heki , Power System & Services Company,Toshiba Corporation; 8,Shinsugita-cho,Isogo-ku, ; Yokohama , 235-8523 JAPAN; Ph: 81-45-770-2384 FAX: 81-45-770-2298 E-mail:Hideaki.heki@toshiba.co.jp
Toney Mathews, AREVA NP; 7207 IBM Drive, CLT-2B, ; Charlotte , NC 28262 USA; Ph: (704) 805-2189 FAX: (704) 805-2675 E-mail:toney.mathews@areva.com

1.01 Advanced BWRs
Tuesday, May 15, 2007 • 8:15-10:00
Hideaki Heki , Power System & Services Company,Toshiba Corporation; 8,Shinsugita-cho,Isogo-ku, ; Yokohama , 235-8523 JAPAN; Ph: 81-45-770-2384 FAX: 81-45-770-2298 E-mail: Hideaki.heki@toshiba.co.jp
Werner Brettschuh, AREVA NP GmbH; , P.O. Box 10 05 51 ; D-63005 Offenbach, Germany; Ph: 49-69-2557-1146 FAX: 49-69-2557-1870 E-mail: werner.brettschuh@areva.com
7105Final An Evolutionary Fuel Assembly Design for High Power Density BWRs 1.01    
7210Final SWR 1000: Diversity in Reactor Protection by Safety I&C and Passive Pressure Puls Transmitter System 1    
7212Final SWR 1000: The Main Design Features of the Advanced Boiling Water Reactor with Passive Safety Systems 1    
7476Final Experimental Verification of SWR 1000 Passive Components and Systems 1.01    
7535Final State-of-the-Art and Prospects for Development of Innovative Simplified Boiling Water Reactor VK-300 1    

1.02 Economics, Regulation, Licensing and Construction
Wednesday, May 16, 2007 • 8:15-10:00
Toney Mathews, AREVA NP; 7207 IBM Drive, CLT-2B, ; Charlotte , NC 28262 USA; Ph: (704) 805-2189 FAX: (704) 805-2675 E-mail: toney.mathews@areva.com
James Tulenko, University of Florida; Nuclear and Radiological Engineering, 202 NSC PO Box 118300; Gainesville, FL 32611-8300 USA; Ph: 352-392-1401 FAX: 352-392-3380 E-mail: tulenko@ufl.edu
7409Final Multi-project, Multi-national, Geographically Dispersed: Challenges for the Nuclear Renaissance in the United States 1    
7177Final Improved Nuclear Fuel Pellet Design to Eliminate the RIM Effect 1   8  
7198Final Establishing and Maintaining Power Conversion System Performance in New Nuclear Power Plants 1   4  
7265Final The Effect of Tropicalization on Steam Generator Blowdown System Design for Standardized Nuclear Power Plant Design 1   4  
7532Final Optimizing NSSS Power and Turbine/Generator Performance for Standardized Nuclear Power Plant Designs in Tropical Climates 1    

1.03 Advanced PWRs-I
Monday, May 14, 2007 • 17:30-19:15
Jean Van Vyve, Tractebel Engineering; Avenue Ariane 7 , ; 1200 Brussels, Belgium; Ph: 32 2 773 77 28 FAX: 32 2 773 76 00 E-mail: Jean.Vanvyve@tractebel.com
Bernard Debontride, AREVA NP; Tour Areva , 92084 Paris-la-Défense ; , France; Ph: 33 1 47 96 17 64 FAX: E-mail: bernard.debontride@areva.com
7576Final APR1400 Severe Accident Mitigation Design    
7286Final Design of APR1400 NSSS Major Components 1    
7056Final Integrated Chemical Effects Tests Program for PWR Sump Performance Assessment 1    
7085Final Roles of Thermal-Hydraulic Experiments for the Development and Licensing of New Safety Features in APR1400 6   1  
7129Final The Development Experience and Design Characteristics of the Advanced Power Reactor 1400 1    

1.03 Advanced PWRs-II
Tuesday, May 15, 2007 • 13:30-15:15
Takashi Kanagawa, Mitsubishi Heavy Industries; Mitsubishi Heavy Industries, Ltd., Nuclear Systems Engineering Dept. 3-1, Minatomirai 3-chome, Nishi-ku; Yokohama , Kanagawa-pref. 220-8401 Japan; Ph: 81-3-6716-4960 FAX: 81-3-6716-5844 E-mail: takashi_kanagawa@mhi.co.jp
Philippe Lauret, AREVA NP; Tour Areva, 92084 PARIS-la-Défense ; , France; Ph: 33-1-47-96-29-57 FAX: 33-1-47-96- 15-09 E-mail: philippe.lauret@areva.com
7578Draft The U.S. EPR: A Standardized Nuclear Power Plant 1.03    
7100Final AP1000 Fuel Design and Core Operations 1   7  
7250Final ACR-1000: Reactor Physics and Fuelling Flexibility 11   7  
7445Final Conceptual Design of OPR-1000 Compatible Annular Fuel Assembly 7    

1.03 Advanced PWRs-III
Tuesday, May 15, 2007 • 17:30-19:15
Takashi Kanagawa, Mitsubishi Heavy Industries; Mitsubishi Heavy Industries, Ltd., Nuclear Systems Engineering Dept. 3-1, Minatomirai 3-chome, Nishi-ku; Yokohama , Kanagawa-pref. 220-8401 Japan; Ph: 81-3-6716-4960 FAX: 81-3-6716-5844 E-mail: takashi_kanagawa@mhi.co.jp
Philippe Lauret, AREVA NP; Tour Areva, 92084 PARIS-la-Défense ; , France; Ph: 33-1-47-96-29-57 FAX: 33-1-47-96- 15-09 E-mail: philippe.lauret@areva.com
7581Final U.S. EPR ITAAC: Coordination with Construction and Startup 1.033    
7260Final Modeling of Silicon Carbide Duplex Cladding Designs for High Burnup Light Water Reactor Fuel 1   8  
7430Final I&C Design Features for Fully Computerized Systems in the US-APWR 1   4  

1.04 Innovative Water Cooled Reactors
Wednesday, May 16, 2007 • 15:30-17:15
Marc Delpech, CEA; CEA CADARACHE, SERI / LCSI BAT. 212; SAINT PAUL LEZ DURANCE, 13108 France; Ph: 33-4-42-25-28-82 FAX: 33-4-42-25-71-87 E-mail: Marc.delpech@cea.fr
Richard Swinburn, Rolls-Royce; Rolls-Royce plc, PO Box 2000 ; Derby, DE21 7XX United Kingdom; Ph: 44 (0)1332 632174 FAX: E-mail: Richard.Swinburn@rolls-royce.com
7417Final SCOR 1000: an Economic and Innovative Conceptual Design PWR 1   10  
7011Final Conceptual Design Study on High Conversion Type Core of FLWR 1    
7389Final Advanced High Conversion PWR: Preliminary Analysis 11   1  
7242Final Components Effects on the Performance of the Passive Residual Heat Removal System of an Advanced Integral Type Reactor 6   5  

Up

2.00: High Temperature Gas Cooled Reactors
Michel Lecomte, AREVA NP; Tour AREVA, ; Paris La Defense Cedex , 92084 France; Ph: 33 147965673 FAX: 33 147961488 E-mail:michel.lecomte@areva.com
Jean-Claude Garnier, CEA; , ; , France; Ph: FAX: E-mail:jean-claude.garnier@cea.fr
Phil MacDonald, Consultant; , ; Cedar Hill , TX USA; Ph: 972-299-9005, 208-521-1208 FAX: 208 526 2930 E-mail:pemcedarhill@yahoo.com
Lewis Lommers, AREVA NP; 3315 Old Forest Road, P.O. Box 10935 ; Lynchburg , VA 24506 USA; Ph: 434-832-3687 FAX: 434-832-3828 E-mail:lewis.lommers@areva.com
Hee Cheon No, KAIST; Nuclear/Hydrogen System Lab., Dep. of Nuclear and Quantum Eng. 373-1 Guseong-dong Yusong-ku ; Daejon, 305-701 Korea; Ph: (042)869-3817 FAX: (042)869-3810 E-mail:hcno@kaist.ac.kr
Michael A. Fütterer, JRC Petten; Institute for Energy, ; NL-1755 ZG Petten , The Netherlands; Ph: 31-224-565158 FAX: 31-224-565615 E-mail:michael.fuetterer@jrc.nl
Zuoyi Zhang, INET; , ; , China; Ph: FAX: E-mail:zyzhang@tsinghua.edu.cn

2.02 Prismatic Fuel Modular Reactors
Wednesday, May 16, 2007 • 15:30-17:15
Alain Capitaine, EDF; 12 - 14 avenue Dutriévoz, ; Villeurbanne, 69130 France; Ph: 04 72 82 74 33 FAX: 04 72 82 77 13 E-mail: alain.capitaine@edf.fr
Michel Lecomte, AREVA NP; Tour AREVA, ; Paris La Defense Cedex , 92084 France; Ph: 33 147965673 FAX: 33 147961488 E-mail: michel.lecomte@areva.com
7130Final A Small High Temperature Gas Cooled Reactor for Nuclear Marine Propulsion 2.02   2.07  
7528Final GAS-NET: A Two-Dimensional Network Code for Prediction of Core Flow and Temperature Distribution in the Prismatic Gas Reactor 2   6  
7375Final Basic Design and Economical Evaluation of Gas Turbine High Temperature Reactor 300 (GTHTR300) 2   10  
7307Final Optimization of TRU Burnup in Modular Helium Reactor 7    

2.03 Test Facilities and Demonstration Reactors for HTR Design and Generic Studies
Monday, May 14, 2007 • 13:30-15:15
Finis Southworth, INEEL; P.O. Box 1625, ; Idaho Falls, ID 83415 USA; Ph: 1-208-526-8150 FAX: 1-208-526-4313 E-mail: fin@inel.gov
Hee Cheon No, KAIST; Nuclear/Hydrogen System Lab., Dep. of Nuclear and Quantum Eng. 373-1 Guseong-dong Yusong-ku ; Daejon, 305-701 Korea; Ph: (042)869-3817 FAX: (042)869-3810 E-mail: hcno@kaist.ac.kr
7566Final RAPHAEL: Materials and Components Highlights from the HTR FP5 and FP6 Programmes 2    
7565Final The (European) HTR Technology Network (HTR-TN) and the Development of HTR Technology in Europe 2    
7474Abs.a Status of Pre-Conceptual Design Studies for the Next Generation Nuclear Plant (NGNP) 2   2  

2.04 Innovative HTRs, Fuels and Materials-I
Tuesday, May 15, 2007 • 8:15-10:00
Michael A. Fütterer, JRC Petten; Institute for Energy, ; NL-1755 ZG Petten , The Netherlands; Ph: 31-224-565158 FAX: 31-224-565615 E-mail: michael.fuetterer@jrc.nl
7204Final High Temperature Corrosion of the Nickel-based Alloy Inconel 617 in Helium containing Small Amounts of Impurities 2    
7175Final Flow Mixing in Pebble Beds and Bundles of Twisted Rods 2   6  
7098Final Low-Enriched Fuel Design Concept for the Prismatic Very High Temperature Reactor Core 2   7  

2.04 Innovative HTRs, Fuels and Materials-II
Tuesday, May 15, 2007 • 13:30-15:15
Werner von Lensa, FZJ Julich; , ; D-52425 Julich, Germany; Ph: 49-2461-61-66-29 FAX: 49-2461-61-53-42 E-mail: w.von.lensa@fz-juelich.de
7119Final Neutronic Studies and Activation Calculations of Different Structural Materials for a Gas-Cooled Fast Reactor 2   3  
7418Final Quality Control of High Temperature Reactors (HTR) Compacts via X-Ray Tomography 2   8  
7305Final Final Assembly and Initial Irradiation of the First Advanced Gas Reactor Fuel Development and Qualification Experiment in the Advanced Test Reactor 2.    

2.06 Power Conversion
Wednesday, May 16, 2007 • 8:15-10:00
Gert Claassen, PBMR (Pty) Ltd; P O Box 9396, ; Centurion, 46 South Africa; Ph: 27 12 677 9400 FAX: 27 12 677 9446 E-mail: gert.claassen@pbmr.co.za
Hee Cheon No, KAIST; Nuclear/Hydrogen System Lab., Dep. of Nuclear and Quantum Eng. 373-1 Guseong-dong Yusong-ku ; Daejon, 305-701 Korea; Ph: (042)869-3817 FAX: (042)869-3810 E-mail: hcno@kaist.ac.kr
7084Final Evaluation for Reasonableness of Power Conversion System Concepts in the Gas Turbine High Temperature Reactor (GTHTR300) 2    
7059Final Nuclear Cogeneration of High Temperature Process Heat and Electricity with Heat Pump Driven Superheating 2   6  
7058Final HTR with Downgraded Specifications for High Temperature Process Heat Applications 2    
7037Final Energy and Economical Analysis of Direct and Indirect Brayton Power Cycles of HTGRs 2   4  
7007Final Power Cycle and Stress Analyses for High Temperature Gas-Cooled Reactor 2   2  

2.07 Modeling and Simulation of HTRs-I
Monday, May 14, 2007 • 17:30-19:15
Pavel Hejzlar, Massachusetts Institute of Technology ; Department of Nuclear Engineering, Rm. 24-215, 77 Massachusetts Ave. ; Cambridge, MA 02139-4307 USA; Ph: 617-253-4231 FAX: E-mail: hejzlar@mit.edu
7381Final Experimental and Computational Analysis of Gas Natural Circulation Loop 2   6  
7240Final An Analysis of a Contact between a Kernel and a Buffer of a TRISO-coated Fuel Particle 2.7    
7234Final Monte Carlo Criticality Calculations for PBMR Core 2   11  
7345Final Rotor Scale Model Tests For Power Conversion Unit of GT-MHR 2    

2.07 Modeling and Simulation of HTRs-II
Tuesday, May 15, 2007 • 17:30-19:15
Steven A. Wright, Sandia National Lab; Sandia National Laboratories, MS1146, PO Box 5800 ; Albuquerque, NM 87185 USA; Ph: 505 845 3014 FAX: E-mail: sawrigh@sandia.gov
7573Final Preliminary Design of a Small Air Loop for System Analysis and Validation of CATHARE Code 2.03    
7052Final Impact of Closed Brayton Cycle Test Results on Gas Cooled Reactor Operation and Safety 2   6  
7172Final Cathare Simulation Of Non Depressurized Transients For The 2400 MW Gas Fast Reactor Concept 2   6  
7171Final Cathare Simulation of a Depressurization Transient for the 2400MW Gas Fast Reactor Concept 2   6  

2.08 Gas Cooled Fast Reactors-I
Wednesday, May 16, 2007 • 13:30-15:15
Mitch Farmer, ANL; Reactor Engineering Laboratory, 9700 S. Cass Avenue ; Argonne , IL 60439-4842 USA; Ph: 630-252-4539 FAX: 630-252-6080 E-mail: farmer@anl.gov
Jean-Claude Garnier, CEA; , ; , France; Ph: FAX: E-mail: jean-claude.garnier@cea.fr
7329Final Control Rod Shadowing and Anti-shadowing Effects in a Large Gas-cooled Fast Reactor 2    
7543Final Thermal Hydraulic and Flow Vibration Analysis of Pin Bundle Designs for the GFR 2    
7330Final A 2D Transient Model for the Gas-cooled Fast Reactor Plate-type Fuel 2    
7208Final Status of the ETDR Design 3    
7350Final CFD Analysis for Flow Behavior Characteristics in the Upper Plenum during Low Flow/ Low Pressure Transients for the Gas Cooled Fast Reactor (GCFR) 2   6  

2.08 Gas Cooled Fast Reactors-II
Wednesday, May 16, 2007 • 15:30-17:15
Colin Mitchel, AMEC NNC; Booths Park, Chelford Road Knutsford; Cheshire WA16 8NQ, UK; Ph: 44 (0) 1565 684843 FAX: 44 (0) 1565 843878 E-mail: CHMitchell@aol.com,Colin.Mitchell@amecnnc.com
Christian Poette, CEA-Cadarache; DER ,Building 212 , 13108 Saint-Paul lez Durance ; , France; Ph: (33) 4 42 25 65 31 FAX: (33)4.42 25 71 87 E-mail: christian.poette@cea.fr
7178Final Status of GFR Pre-conceptual Design Study 2   3  
7342Final The DHR Systems of the GFR, Preliminary Design and Safety Analysis    
7340Final A GFR Benchmark Comparison of Transient Analysis Codes Based on the ETDR Concept 6   3  
7274Abs.a Uncertainties and Safety Margins for the Determination of Pressure within the GFR's Containment 5   2  
7292Final Nuclear Facility with the Gas Cooled Fast Reactor BGR-1000 Using Coated Particles and Technologies of Light Water Reactors 2    

Up

3.00: Long Term Reactor Programs and Strategies
Claude Renault, CEA/DEN/DDIN; CEA Saclay, ; Gif-sur-Yvette, F-91191 France; Ph: (33) 1 69 08 63 95 FAX: (33) 1 69 08 58 92 E-mail:claude.renault@cea.fr
Jacopo Buongiorno, MIT; Massachusetts Institute of Technology, Dept of Nuclear Engineering, Room 24-206 77 Massachusetts Ave; Cambridge, Massachusettes 02139-4307 USA; Ph: 617-253-7316 FAX: 617-258-8863 E-mail:jacopo@mit.edu
Pavel Alekseev, ; , ; , Russia; Ph: FAX: E-mail:apn@dhtp.kiae.ru
Dohee Hahn, KAERI; Korea Atomic Energy Research Institute, Yuseong P.O.Box 105, ; Daejeon, 305-600 Korea; Ph: 82-42-868-8725 FAX: E-mail:hahn@kaeri.re.kr
Masakazu ICHIMIYA, Japan Atomic Energy Agency (JAEA); Tsuruga Head Office, 65-20, Kizaki, Tsuruga, Fukui ; , 914-8585 Japan; Ph: 81 770 23 3021 FAX: 81 770 21 5090 E-mail:ichimiya.masakazu@jaea.go.jp

3.01 Sodium-cooled Fast Reactors-I
Wednesday, May 16, 2007 • 8:15-10:00
Masakazu ICHIMIYA, Japan Atomic Energy Agency (JAEA); Tsuruga Head Office, 65-20, Kizaki, Tsuruga, Fukui ; , 914-8585 Japan; Ph: 81 770 23 3021 FAX: 81 770 21 5090 E-mail: ichimiya.masakazu@jaea.go.jp
Philippe Martin, CEA; , ; , France; Ph: FAX: E-mail: philippe.martin@cea.fr
7567Draft A Loop Sodium Reactor with a Cold Resting Bottom Vessel 3    
7408Final Studies of Passive Safety Tests by Using Experimental Fast Reactor Joyo - Verification of Joyo Plant Dynamics Analysis Code Mimir-N2 11    
7348Final BN-800 Reactor is a New Stage in Transition to Innovative Nuclear Power 3   10  
7308Final Neutronic Characterization of Sodium-cooled Fast Reactor in an MHR-SFR Synergy for TRU Transmutation 11    

3.01 Sodium-cooled Fast Reactors-II
Wednesday, May 16, 2007 • 13:30-15:15
Jacques Rouault, CEA; , ; , France; Ph: FAX: E-mail: jrouault@cea.fr
7452Abs.a A Comparative Analysis of Sodium-cooled and Gas-cooled Fast Reactors 3   2  
7547Final Investigation of Sodium - Carbon Dioxide Interactions with Calorimetric Studies 3    
7383Final Innovating Core Design for Generation IV Sodium Cooled Fast Reactors 3   11  
7301Final A Concept of Prospective Sodium Fast Reactor with Ductless Fuel Subassemblies in the Core 3    
7263Final Core Design Studies for Advanced Burner Test Reactor 3   7  

3.01 Sodium-cooled Fast Reactors-III
Wednesday, May 16, 2007 • 15:30-17:15
Baldev Raj, Indira Gandhi Centre for Atomic Research; Kalpakkam 603 102, ; , India; Ph: 91(044)27480240 FAX: 91(044)27480301 E-mail: secdmg@igcar.gov.in
Dohee Hahn, KAERI; Korea Atomic Energy Research Institute, Yuseong P.O.Box 105, ; Daejeon, 305-600 Korea; Ph: 82-42-868-8725 FAX: E-mail: hahn@kaeri.re.kr
7506Final A New Design Concept of the KALIMER-600 Reactor Core 3    
7398Abs.a A Program on Innovative SFR in France 3    
7376Final Characteristics of Fast Reactor Core Designs and Closed Fuel Cycle 3   3  
7132Final Thermal Analysis on Shipping Cask for LMFR Fresh Trans-Uranium Fuel Transportation 3   7  

3.02 Lead-cooled Fast Reactors
Wednesday, May 16, 2007 • 8:15-10:00
Luciano Cinotti, DFGE; , ; , Italy; Ph: FAX: E-mail: luciano.cinotti@delfungogieraenergia.com
Craig F. Smith, LLNL; Lawrence Livermore National Laboratory, L-632, P.O. Box 808 ; Livermore, CA 94550 USA; Ph: 925-423-1772 FAX: 925-422-9913 E-mail: smith94@llnl.gov
7497Final Multiphase Flow Phenomena of Steam Generator Tube Rupture in a Lead-Cooled Reactor System: A Scoping Analysis 3.02   5  
7536Final Progresses in the Operation of Large Scale LBE Loop: HELIOS 3   4  
7469Final Safety Features of a Pb-Bi Cooled Transmutation Reactor 3.02    
7280Final Safety Design/Analysis and Scenario for Prevention of CDA with ECCS in Lead-Bismuth-Cooled Fast Reactor 3   5  
7193Final Lead-Cooled Fast Reactors with Th-based Fuels - Neutronics and Safety 3   7  
7015Final Advanced Burner Test Reactor Concept 3   12  

3.03 Supercritical Water Reactors
Tuesday, May 15, 2007 • 13:30-15:15
Joerg Starflinger, FZK; Forschungszentrum Karlsruhe GmbH, IKET, Bldg. 420 Hermann-von-Helmholtz-Platz 1; , ; Ph: FAX: E-mail: joerg.starflinger@iket.fzk.de
Hussam Khartabil, AECL; , ; , Canada; Ph: FAX: E-mail: khartabilh@aecl.ca
7206Final A Study of Fuel Behavior in a SCWR Core with High Power Density 1    
7124Final SuperCritical Light Water Reactor with Intermediate Heat Exchangers 1    
7502Final Conceptual Design of 1400 MWe Supercritical Water Cooled Reactor Core Design with a Cruciform Type of U/Zr Solid Moderator 1   1  
7494Final Preliminary Calculations of Coolant Flow in a SCWR Fuel Assembly with the Code ANSYS CFX 10.0 3   6  
7423Final Neutron-Physical and Thermal-Hydraulic Characteristics of a New SCWR Fuel Assembly 3.03    
7309Final Safety Characteristics of the Super LWR Design Concept 5    

3.04 Molten Salt and Liquid Salt Reactors
Monday, May 14, 2007 • 13:30-15:15
Charles Forsberg, Oakridge National Laboratory; P.O. Box 2008, 1 Bethel Valley Road ; Oak Ridge, TN 37831-6165 USA; Ph: 865-574-6783 FAX: (865) 574-0382 E-mail: forsbergcw@ornl.gov
Claude Renault, CEA/DEN/DDIN; CEA Saclay, ; Gif-sur-Yvette, F-91191 France; Ph: (33) 1 69 08 63 95 FAX: (33) 1 69 08 58 92 E-mail: claude.renault@cea.fr
7424Final MSR – SPHINX Concept Program EROS (Experimental zeRO power Salt reactor SR-0): The Proposed Experimental Program as a Basis for Validation of Reactor Physics Methods 11.04   11.03  
7548Final Progress in Development of Na,Li,Be/F Molten Salt Actinide Recycler & Transmuter Concept 3   7  
7186Final Optimized Transition from the Reactors of Second and Third Generations to the Thorium Molten Salt Reactor 3    
7405Final Fuel Geometry Options for Salt-Cooled Advanced High-Temperature Reactors 3   2  

3.06 Liquid Metal Fast Reactors (SFR/LFR)
Wednesday, May 16, 2007 • 15:30-17:15
Joel Guidez, CEA; , ; , France; Ph: FAX: E-mail: joel.guidez@cea.fr
V.N. Karaulov, NIKIET-Russia; , ; , ; Ph: FAX: E-mail: glazov@nikiet.ru
7545Final Numerical Optimization of Wire-Wrapped Fuel Assembly of Liquid Metal Reactor with 3-D RANS Analysis 3   6  
7499Final Self-organized Regime of Nuclear Burning Wave in Safe Fast Reactor 3   11  
7303Final Power DRAC for Rapid LMFBR Deployment and Consequent CO2 Mitigation 3    
7133Final Active Zone of the Safe Fast Uranium-Plutonium Reactor Working Without a Reactivity Margin During Long Time 3   11  
7104Final Liquid Metal Cooled Variable Geometry Reactor Structure 3    

3.07 Innovative Conversion Systems
Monday, May 14, 2007 • 17:30-19:15
Jacopo Buongiorno, MIT; Massachusetts Institute of Technology, Dept of Nuclear Engineering, Room 24-206 77 Massachusetts Ave; Cambridge, Massachusettes 02139-4307 USA; Ph: 617-253-7316 FAX: 617-258-8863 E-mail: jacopo@mit.edu
Patrick Dumaz, CEA; , ; , France; Ph: FAX: E-mail: patrick.dumaz@cea.fr
7072Final Supercritical CO2 Gas Turbine Cycle Systems 3   12  
7071Final Efficiency Improvement of the Indirect Supercritical CO2 Turbine System for Fast Reactors by Applying Micro-Channel Intermediate Heat Exchanger 3   12  
7039Final Design Study for CO2-Na Reaction Events of Super-Critical CO2 Indirect Cycle Gas Turbine Fast Reactor 3    

Up

4.00: Operation, Performance & Reliability Management
Philippe Taurin, EDF; Site Cap Ampère, 1 tour Pleyel 93282 St-Denis cédex; , France; Ph: 33 1 43 69 32 55 FAX: 33 1 43 69 34 74 E-mail:philippe.taurin@edf.fr
Isabelle Morlaes, AREVA NP; Tour AREVA , 92084 Paris la Défense Cedex ; , France; Ph: 33 1 47 96 28 03 FAX: E-mail:isabelle.morlaes@areva.com
Joel Woodcock, Westinghouse Electric Company; Waltz Mill Site, P.O. Box 158 , P.O. Box 355 ; Madison, PA 15663 USA; Ph: (1) 724-722-6020, (1) 412-760-4641 FAX: (1) 724-722-5597 E-mail:woodcoj@westinghouse.com
Kwon Hoie Koo, KHNP; , ; , Korea; Ph: FAX: E-mail:koo@khnp.co.kr

4.01 Industry Initiatives to Optimize Outage
Wednesday, May 16, 2007 • 8:15-10:00
Joel Woodcock, Westinghouse Electric Company; Waltz Mill Site, P.O. Box 158 , P.O. Box 355 ; Madison, PA 15663 USA; Ph: (1) 724-722-6020, (1) 412-760-4641 FAX: (1) 724-722-5597 E-mail: woodcoj@westinghouse.com
7561Final Chemical Degassing on EDF Units - Feed Back Experience and Method 4    
7400Final Knowledge Integrated Management System for Maintenance Service at NPP ISAR 4    
7358Final On-line 4-face Colour CCD Fuel Inspection During Offload 4   7  
7219Final Shortened Outage Duration and Increased Safety with Head Assembly Upgrade Packages 4   1  
7190Final Permanent Cavity Seal Ring for Narrow Gap Pressurized Water Reactor Applications 4   1  

4.02 Industry Initiatives to Improve Performance and Reliability-I
Tuesday, May 15, 2007 • 8:15-10:00
Philippe Clergue, AREVA; , ; , France; Ph: FAX: E-mail:
Manfred Blank, AREVA; , ; , ; Ph: FAX: E-mail:
7203Final Application of Improved Technologies for Ensuring High Quality in Safety, Maintenance and Operation Activities of Units 5&6 of Kozloduy - A Successful Project 4    
7142Final An Approach to Reduce Measurement Uncertainty of Fuel Channel Coolant Flow Rate for CANDU Plants with an CROSSFLOW Ultrasonic Flow Meter 4   5  
7067Final Safety Relief Valves Serviceability Enhancement by Spring Compression Stability    
7412Final Nonlinear Dynamic Characteristics and Stability of LPM Type CEDM 4   1  
7347Final Steam Generator Asset Management Model Overview 4    

4.02 Industry Initiatives to Improve Performance and Reliability-II
Tuesday, May 15, 2007 • 13:30-15:15
Philippe Clergue, AREVA; , ; , France; Ph: FAX: E-mail:
Manfred Blank, AREVA; , ; , ; Ph: FAX: E-mail:
7563Final Design and Installation of Upgraded Retrofit ECCS Sump Strainers 4    
7395Final Advanced Monitoring Systems for Nuclear Power Plants 4    
7147Final A Prediction Method based on Grey System Theory in Equipment Condition based Maintenance 4    
7108Final Implementation of Uncertainty Analysis in Evaluation of Small Disturbances 4    
7036Final Modernization of Kernkraftwerk Beznau's Core Monitoring System with Studsvik Scandpower's GARDEL System 4   11  

4.03 In-service Inspection
Wednesday, May 16, 2007 • 13:30-15:15
François Champigny, EDF; , ; , France; Ph: FAX: E-mail: francois.champigny@edf.fr
7438Final Nuclear Containment Systems and Inservice Inspection Status of Korea Nuclear Power Plants 4   5  
7359Final Non destructive Examinations and Degradations: The Use of Feedback Experience to Improve Maintenance Policy 4    
7226Draft Development of Piping Thickness Monitoring System using Equipotent Switching Direct Current Potential Drop Method 4   8  
7360Final NDE Qualification Process at EDF 4    
7460Abs.a A Flow Analysis in the Surroundings of the Impingement Baffle of the Extracting Nozzle for Disclosing Shell Wall Thinning of a Feedwater Heater 4   6  

4.04 Industry Initiatives to Manage the Impact of Materials Aging Degradation
Monday, May 14, 2007 • 13:30-15:15
Pascal Blin, EDF; , ; , France; Ph: FAX: E-mail:
7353Final Extended Scope and Responsibility in Large Component Replacements 4    
7230Final Wall Thinning Trend for Carbon Steel Piping of OPR-1000 4   1  
7060Final Application of Risk-informed Approaches for Optimization of Control of WWER 1000 Pipelines Metal 4   5  

4.05 Human Reliability and Operations
Monday, May 14, 2007 • 17:30-19:15
Denis Lecocp, AREVA; , ; , ; Ph: FAX: E-mail:
Mark Reinhart, IAEA; , ; , ; Ph: FAX: E-mail: F.Reinhart@iaea.org
7109Final Creating a Culture Where Employee Engagement Thrives 5    
7148Final A Human-Centered Approach Based on Multilevel Flow Models for Diagnosing Fault In Nuclear Power Plant 4    
7064Final Human Factors Engineering Applied to the Design of New Nuclear Power Plants 4    
7517Final Human Performance for the Success of Equipment Reliability Programs 4    

Up

5.00: Plant Safety Assessment and Regulatory Issues
Christian Clément, EDF; , ; , France; Ph: 33 4 72 82 72 07 FAX: E-mail:christian.clement@edf.fr
Nam Dinh, Royal Institute of Technology in Stockholm; , ; , Sweden; Ph: 46 8 790 9255 FAX: E-mail:nam.dinh@energy.kth.se
Paul Coddington, Paul Scherrer Institute; OVGA/319, Paul Scherrer Institute ; CH-5232 Villigen PSI , SWITZERLAND; Ph: 41-56-310-2738 (office) FAX: 41-56-310-2199 (central) E-mail:Paul.Coddington@psi.ch
Sandra Sloan, AREVA NP; 3315 Old Forest Road, Lynchburg, VA 25406 ; , USA; Ph: 434-832-2369 FAX: E-mail:sandra.sloan@areva.com
Cesare Frepoli, Westinghouse; P.O. Box 355, ; Pittsburgh, PA 15230-0355 USA; Ph: (412) 374 4156 FAX: (412) 374 5139 E-mail:FrepolC@westinghouse.com
Kazuo ISHIGUMA, Japan Atomic Power Company; , ; , Japan; Ph: 81-3-4415-6602 FAX: 81-3-4415-6690 E-mail:kazuo-ishiguma@japc.co.jp

5.01 LOCA Plant Analysis and Methodologies-I
Tuesday, May 15, 2007 • 8:15-10:00
Jonathan Birchley, Paul Scherrer Institute; Laboratory for Safety and Accident Research, ; Villigen , Switzerland; Ph: +41 56 310 2724 FAX: +41 56 310 2199 E-mail: jonathan.birchley@psi.ch
7365Final Licensing in Be System Code Calculations: Applications and Uncertainty Evaluation by CIAU Method 6   5  
7498Final Development of CIAU Database for NPP Safety Analysis by Cathare 2 Code 5    
7406Final Study of the Transients of Loss of Coolant Accident in an Installation Pressurized with the RELAP5/mod3.2 Code System 5   1  
7047Final Thermal Hydraulic Analysis of CANDU 6 100% Reactor Outlet Header Break Using RELAP5 Code 5    

5.01 LOCA Plant Analysis and Methodologies-II
Tuesday, May 15, 2007 • 13:30-15:15
Sandra Sloan, AREVA NP; 3315 Old Forest Road, Lynchburg, VA 25406 ; , USA; Ph: 434-832-2369 FAX: E-mail: sandra.sloan@areva.com
7525Final The Approach to the Optimization of the NPP Characteristics on a Basis of the Use of Best Estimate Codes and of Information Technologies 5    
7377Final Parameter Changes of Core Designs and Safety Analyses Due to Power Uprate in Kori 3&4 and Yonggwang 1&2 4    
7184Final Thermal Hydraulic Analysis of LOCA for Justification of RBMK-1500 Success Criteria 6   5  

5.02 Development in Severe Accident Analysis, Codes and Management
Monday, May 14, 2007 • 13:30-15:15
Eric Williams, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2779 FAX: E-mail: Eric.Williams@areva.com
Pascal Gandrille, AREVA NP SAS; TOUR AREVA, ; Paris, 92084 La Défense CEDEX, France; Ph: 33 (0)1-47-96-29-10 FAX: 33 (0)1-47-96-01-48 E-mail: Pascal.Gandrille@areva.com
7489Final AP-1000 Passive In-Vessel Retention Design for a Severe Accident 5    
7512Final A Study of Ex-Vessel Debris Formation in a LWR Severe Accident 5    
7106Final Enhancement of the In-Vessel Retention Capabilities of Advanced Light Water Reactors through the Use of Nanofluids 5.02    
7560Final Severe Damage Analysis of VVER 1000 Following a Large Break LOCA Using ASTEC Code 5   1  
7121Final Improved FFTBM by Signal Mirroring as a Tool for Code Assessment 6   5  
7027Draft Study on Entry Criteria for Severe Accident Management during Hot Leg LBLOCAs in a PWR 5   6  

5.03 Severe Accident Phenomena: Experiment and Modeling-I
Tuesday, May 15, 2007 • 8:15-10:00
Weimin Ma, Royal Institute of Technology; Roslagstullsbacken 21, ; Stockholm, 106 91 Sweden; Ph: 46-8-5537 8821 FAX: 46-8-5537 8830 E-mail: ma@safety.sci.kth.se
7484Final Thermo-physical Properties of Corium: Development of an Assessed Data Base for Severe Accident Application 8    
7328Final Oxide-Metal Corium-concrete Interaction Test in the VULCANO Facility 6   5  
7327Final Thermitic Melting of Prototypic Corium at the PLINIUS Platform 6   8  
7275Final Layer Inversion Tests with Metal-added Corium in the TROI Experiment 5    
7552Final Severe Fuel Damage Analysis for PHEBUS - FP Tests 5   5  

5.03 Severe Accident Phenomena: Experiment and Modeling-II
Tuesday, May 15, 2007 • 13:30-15:15
Eric Williams, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2779 FAX: E-mail: Eric.Williams@areva.com
7544Final A Summary of Findings from the Melt Coolability and Concrete Interaction (MCCI) Program 5    
7521Final Predictability of Iodine Chemistry in the Containment of a Nuclear Power Plant under Hypothetical Severe Accident Conditions 5   6  
7337Final The Results From the Second High-Pressure Melt Ejection Test Completed in the Molten Fuel Moderator Interaction Facility at Chalk River Laboratories 5    
7312Final Crust Formation and Dissolution during Corium-concrete Interaction 6   5  

5.03 Severe Accident Phenomena: Experiment and Modeling-III
Tuesday, May 15, 2007 • 17:30-19:15
T. (Nithy) Nitheanandan, AECL - Chalk River Laboratories ; Fuel Channel Behaviour Section , Fuel & Fuel Channel Safety Branch ; Chalk River, Ontario Canada; Ph: (613) 584-8811 Ext 4954 FAX: (613) 584-8148 E-mail: nitheanandant@aecl.ca
7300Final Computation and Analysis of the Direct Containment Heating Dispersion Process with the Multiphase Flow Software MC3D 5.03    
7299Final Analysis of the Thermal Fragmentation as a Mechanism for the Initiation of Steam Explosion 5.03    
7031Final VVER-1000/V320 Decay Heat Analysis, Involving TVS-M and TVS-A Fuel Assemblies 5   7  
7028Final Regulatory Assessment of Severe Accident Management Guideline for Kori-1 NPP 5   6  

5.04 Development in Life Extension Issues and in Regulatory Safety Assessment
Wednesday, May 16, 2007 • 8:15-10:00
Christian Clément, EDF; , ; , France; Ph: 33 4 72 82 72 07 FAX: E-mail: christian.clement@edf.fr
7341Final Life Assessment and Ageing Management of LOCA Qualified Electrical Equipment 5    
7287Final German Nuclear Power Plants Utility Ageing Management (AM) - Current AM-Activities 5    
7126Final Optimized Maintenance Concept of Safety Relevant Valves Related to Ageing Management Features in Nuclear Power Plants 5    
7583Final Contribution of Enterprise Asset Management (EAM) Systems and CAP Programs to Support NPP Life Extension Program 5.04    

5.06 PRA and Risk Informed Decision Making: Methodology and Advances in Practice-I
Wednesday, May 16, 2007 • 13:30-15:15
Kazuo ISHIGUMA, Japan Atomic Power Company; , ; , Japan; Ph: 81-3-4415-6602 FAX: 81-3-4415-6690 E-mail: kazuo-ishiguma@japc.co.jp
Dan Serbanescu, EC-DG JRC-Institute of Energy-The Netherlands; , ; , ; Ph: FAX: E-mail: dan.serbanescu@jrc.nl
7477Final Dealing with Phenomenological Uncertainties in PRAs for Risk-Informed Decisions 5    
7470Final Application of PSA Methodology for Optimization of Repair, Maintenance and Tests Modes of the Equipment of NPPs with RBMK Types Reactors 5   4  
7153Final The Development of a HRA Calculator for Nuclear Power Plants 5.6    
7001Final Some Aspects of Integrating Risk and Security Aspects for Complex Systems Analyses 5   9  

5.06 PRA and Risk Informed Decision Making: Methodology and Advances in Practice-II
Wednesday, May 16, 2007 • 15:30-17:15
Kazuo ISHIGUMA, Japan Atomic Power Company; , ; , Japan; Ph: 81-3-4415-6602 FAX: 81-3-4415-6690 E-mail: kazuo-ishiguma@japc.co.jp
Mark Reinhart, IAEA; , ; , ; Ph: FAX: E-mail: F.Reinhart@iaea.org
7513Final A Probabilistic Approach for the Determination of Extreme Actions with Respect to the Structural Design 5   8  
7158Final Development and Verification of a Leningrad NPP Unit1 Living PSA-Model in the INL SAPHIRE Code Format for Prompt Operational Safety Level Monitoring 5   5  
7083Final Risk-Informed Decision Making - A Keystone in Advanced Safety Assessment 5    

5.07 Development in Safety Analysis Methodologies for Future Plants-I
Wednesday, May 16, 2007 • 13:30-15:15
Sandra Sloan, AREVA NP; 3315 Old Forest Road, Lynchburg, VA 25406 ; , USA; Ph: 434-832-2369 FAX: E-mail: sandra.sloan@areva.com
7168Final Safety Approach for the Design and the Assessment of Future Nuclear Systems 5   3  
7486Final Stochastic Safety Analysis of Natural Circulation Decay Heat Removal in Liquid Metal Reactor 5    
7349Final Evolutionary Approaches for the Safety Evaluation of the Nuclear Fuel Cycle Facilities: Lessons Learnt from French Experience and Assessment of Future Challenges 5   7  
7066Final Application of Best Estimate Methodology to MTR Research Reactors 5    

5.07 Development in Safety Analysis Methodologies for Future Plants-II
Wednesday, May 16, 2007 • 15:30-17:15
Gian-Luigi Fiorini, CEA; CEA/Saclay, DEN/DDIN bat 121 ; 91191 Gif sur Yvette Cedex , France; Ph: 33 1 69 08 63 95 FAX: 33 1 60 08 58 92 E-mail: gian-luigi.fiorini@cea.fr
7111Final Development of a PSA Information Management System 5   4  
7082Final Towards Standardizing Uncertainty Estimations in Reactor Safety 6    
7040Final Uncertainty Analysis of the PBMR Reactor Unit Seismic Response    

5.08 Non-LOCA Plant Analysis and Methodologies
Monday, May 14, 2007 • 13:30-15:15
Tomasz Kozlowski, Royal Institute of Technology; Nuclear Power Safety Division, Roslagstullsbacken 21 ; Stockholm, 10691 Sweden; Ph: 46-8-553-788-22 FAX: 46-8-553-788-30 E-mail: Tomasz@safety.sci.kth.se
Jonathan Birchley, Paul Scherrer Institute; Laboratory for Safety and Accident Research, ; Villigen , Switzerland; Ph: +41 56 310 2724 FAX: +41 56 310 2199 E-mail: jonathan.birchley@psi.ch
7478Final A Study of Reactor Systems During a Loss of Offsite Electric Power in Forsmark-1 Plant 5    
7115Final Output Signal Analysis for Variation of R-C Passive Elements in the 4~2mA R-L-C Equivalent Circuit Modeling under High Temperature Accident Condition in NPPs 4   5  
7014Final MELCOR Analysis of Loss of Residual Heat Removal during Mid-loop Operation in a Westinghouse Two-loop PWR 5    
7555Final Validation of CATHENA Fuel Channel Model for Post Blowdown Analysis against High Temperature Thermal-Chemical Experiment for Aged CANDU Fuel Channel 11    
7213Final Development of Additional Module to Neutron-Physic and Thermal-Hydraulic Computer Codes for Coolant Acoustical Characteristics Calculation 11    
7432Final Simulation Technology to Develop the Automatic Control Rod Operation System in ABWR 4   11  

5.08 Non-LOCA Plant Analysis and Methodologies-II

5.09 Containment and non-Radiological Inventory
Wednesday, May 16, 2007 • 8:15-10:00
Cesare Frepoli, Westinghouse; P.O. Box 355, ; Pittsburgh, PA 15230-0355 USA; Ph: (412) 374 4156 FAX: (412) 374 5139 E-mail: FrepolC@westinghouse.com
7436Final Performance Analysis of the Recirculation Sump in Kori 1 NPP for the Resolution of GSI-191 5   4  
7245Final Calculation of Flow Field and Debris Transport during Blowdown/Washdown Phases 5   1  
7143Final Effects of Debris Source, Chemical Environments, and Design Options on the ECCS Recirculation Sump Performance 6   5  
7475Final Experimental Study of Plant Specific Head Loss Induced by LOCA-generated Debris at Containment Sump of PWR 1   5  
7285Final Modelling of Nonhomogeneous Atmosphere in NPP Containment Using Lumped-Parameter Model Based on CFD Calculations 6    
7044Final Fragility Analysis for Pressure Capacity of ESBWR Primary Containment System 5   8  

5.10 Radiological Inventory and Emergency Situations
Tuesday, May 15, 2007 • 17:30-19:15
Christian Clément, EDF; , ; , France; Ph: 33 4 72 82 72 07 FAX: E-mail: christian.clement@edf.fr
7471Final CFD Study for Aerosol Deposition in Turbulent Isokinetic Sampling Probe 5   6  
7425Final Development of Dose Assessment Program to Recommend Emergency Protective Actions for Public 5   9  
7090Final Ruthenium Transport Experiments in Air Ingress Accidents Conditions 5    

Up

6.00: Thermal Hydraulic Analysis and Testing
Bernard Faydide, CEA; CEA/Grenoble, DEN/DER/SSTH, 17, Rue des Martyrs 38054 Grenoble Cedex 9; , France; Ph: (33) 4 38 78 40 53 FAX: (33) 4 38 78 57 28 E-mail:bernard.faydide@cea.fr
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail:nusret.aksan@psi.ch
Izumi KINOSHITA, CRIEPI; 2-11-1, Iwado-kita,, ; Komae-shi, Tokyo 201-8511 Japan; Ph: 81-3-3480-2111 FAX: 81-3-3480-7950 E-mail:kinosita@criepi.denken.or.jp
Won-Pil Beak, KAERI; , ; , Korea; Ph: FAX: E-mail:wpbaek@kaeri.re.kr
Richard F. Wright, Westinghouse Electric Co.; MEC-324, P.O. Box 355 ; Pittsburgh , PA 15230 USA; Ph: 412-374-4719 FAX: 412-374-5005 E-mail:wrightrf@westinghouse.com
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, ; Collage Station , TX 77843-3133 USA; Ph: 409-845-7090 FAX: 409-845-6443 E-mail:y-hassan@tamu.edu
Akira Ohnuki, Japan Atomic Energy Agency (JAEA); , ; , Japan; Ph: 81 29 267 4141 ex. 5617 FAX: 81 29 267 1676 E-mail:ohnuki.akira@jaea.go.jp

6.01 Advances in Two-Phase Flow & Heat Transfer
Monday, May 14, 2007 • 13:30-15:15
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, ; Collage Station , TX 77843-3133 USA; Ph: 409-845-7090 FAX: 409-845-6443 E-mail: y-hassan@tamu.edu
7319Final Towards the Prediction of Local Thermal-hydraulics in Real PWR Core Conditions Using NEPTUNE_CFD Software 6    
7257Final Mechanistic Multidimensional Analysis of Two-Phase Flow in Horizontal Tube with 90° Elbow 6    
7256Final Effect of Physical Properties of Fluids at Supercritical Conditions on Local Flow and Heat Transfer in Heated Channels 6   1  

6.02 Advances in CHF and Rod Bundle Thermal Hydraulics
Monday, May 14, 2007 • 17:30-19:15
Hae-Yong Jeong, KAERI; 150 Dugjin-dong, Yuseong-gu ; Daejeon, 305-353 Korea; Ph: 82-42-868-8987 FAX: 82-42-868-2075 E-mail: hyjeong@kaeri.re.kr
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, ; Collage Station , TX 77843-3133 USA; Ph: 409-845-7090 FAX: 409-845-6443 E-mail: y-hassan@tamu.edu
7549Final Thermal Hydraulics Performance Optimization of CANDU Fuel Using ASSERT Subchannel Code 6    
7233Final Subchannel Flow Analysis in CANDU and ACR Pressure Tubes with Radial and Axial Flow Tube Diameter Variation 6   1  
7269Final Inter-Subchannel Heat Transfer Modeling for a Subchannel Analysis of Liquid Metal-Cooled Reactors 6   6.02  
7264Final Lessons Learned from the Quench-11 Training Exercise 6   1  

6.03 CFD Applications to Water, Liquid Metal, and Gas Reactors-I
Tuesday, May 15, 2007 • 8:15-10:00
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, ; Collage Station , TX 77843-3133 USA; Ph: 409-845-7090 FAX: 409-845-6443 E-mail: y-hassan@tamu.edu
7216Final A Computational Approach for the Performance Prediction of High Temperature Heat Exchangers 2    
7165Final An Effective Convectivity Conductivity Model for Simulation of In-Vessel Core Melt Progression in Boiling Water Reactor 6   6  
7092Final Development of an Euler-Euler Two-Phase Model for Application in the Windowless XT-ADS Spallation Target Design 6   7  
7481Final Detached Eddy Simulation and Large Eddy Simulation Models for the Simulation of Gas Entrainment 6   1  
7479Final Numerical Investigations of Different Geometrical Designs of the Windowless XT ADS Spallation Target 6    

6.03 CFD Applications to Water, Liquid Metal, and Gas Reactors-II
Tuesday, May 15, 2007 • 13:30-15:15
Richard F. Wright, Westinghouse Electric Co.; MEC-324, P.O. Box 355 ; Pittsburgh , PA 15230 USA; Ph: 412-374-4719 FAX: 412-374-5005 E-mail: wrightrf@westinghouse.com
7069Final Flow Distribution Analysis in a Nuclear Steam Generator Tube Bundle Using Computational Fluid Dynamics 6   4  
7448Final Feasibility Study on Debris Transport Analysis in Recirculation Mode Using Three Dimensional Computational Fluid Dynamics Code 6   03  
7431Final Sensitivity Study of CFD Turbulent Models for Natural Convection Analysis 6   6  
7310Final RANS and URANS Simulations for Accurate Flow Predictions inside Fuel Rod Bundles 7    
7075Final Test of Large Eddy Simulation Sub-Grid-Scale Models for Flows in Annular Channels 6   1  

6.04 Separate Effects Thermal Hydraulic Experiments & Analysis-I
Monday, May 14, 2007 • 13:30-15:15
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail: nusret.aksan@psi.ch
7510Final Numerical Investigation of Sodium-Water Reaction Phenomenon in a Tube Bundle Configuration 6   3  
7361Final Heat Transfer and Average Friction Coefficients for Laminar, Transitional and Turbulent Flow of Gas (N2, He, He-N2) in a Cylindrical Tube 6   2  
7357Final Horizontal-Jets Impinging on the Vertical Wall of a Containment Compartment 6    
7279Final Condensation Heat Transfer on Natural Convection at the High Pressure 6   6  

6.04 Separate Effects Thermal Hydraulic Experiments & Analysis-II
Monday, May 14, 2007 • 17:30-19:15
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail: nusret.aksan@psi.ch
7191Final HORUS3D/TH: Thermal-Hydraulic Modelling of the Jules Horowitz Reactor Core with FLICA4 6   11  
7144Final Modeling of High Pressure Steam Condensation in the Presence of Noncondensable Gas in a Vertical Tube with a Secondary Pool Condition 6    
7026Final Gas Entrainment in Scaled Model of Pool Type LMFBR 6   3  

6.05 Integral Systems Thermal Hydraulic Experiments-I
Tuesday, May 15, 2007 • 8:15-10:00
Bernard Faydide, CEA; CEA/Grenoble, DEN/DER/SSTH, 17, Rue des Martyrs 38054 Grenoble Cedex 9; , France; Ph: (33) 4 38 78 40 53 FAX: (33) 4 38 78 57 28 E-mail: bernard.faydide@cea.fr
7550Final Integral Experiment and RELAP5 Analysis for DVI Line Break SBLOCA in APR1400 6    
7492Final Code Validation and Scalation of the LOBI BL-30 Experiment 6.05   6.06  
7453Final Effect on Code Predictions by Changing the Code Version of Relap5 on SBLOCA for Test 9.1B in BETHSY Test Facility 6   5  
7202Final PSB-VVER Experimental and Analytical Investigation of Station Blackout Accident in VVER-1000 6    
7131Final An Experimental Study on Natural Draft-dry Cooling Tower as Part of the Passive System for the Residual Decay Heat Removal 6    

6.05 Integral Systems Thermal Hydraulic Experiments-II
Tuesday, May 15, 2007 • 17:30-19:15
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail: nusret.aksan@psi.ch
Bernard Faydide, CEA; CEA/Grenoble, DEN/DER/SSTH, 17, Rue des Martyrs 38054 Grenoble Cedex 9; , France; Ph: (33) 4 38 78 40 53 FAX: (33) 4 38 78 57 28 E-mail: bernard.faydide@cea.fr
7490Final CATHARE 2 Prediction of Large Primary to Secondary Leakage (PRISE) at PSB-VVER Experimental Facility 6    
7222Final Numerical Modeling of the OSU MASLWR Test Facility using RELAP5-3D 6   1  
7091Final Thermal-Hydraulic Experimental Investigations on Safety of NPP with VVER 6   5  
7073Final Capability of the Best Estimate Code RELAP5/MOD3.2 to Analyze the Steady State and Stability of Boiling Two-Phase Natural Circulation Systems 4   6  

6.06 Systems Analysis & Assessment-I
Wednesday, May 16, 2007 • 13:30-15:15
Francesco D’Auria, Università di Pisa; Dipartimento di Ingegneria, Meccanica, Nucleare e della Prodzione (DIMNP) Via Diotisalvi, 2; I-56126 Pisa, Italy; Ph: 39 050 836653 FAX: 39 050 836665 E-mail: dauria@ing.unipi.it
7434Final Hydrogen Distribution Analysis for PHWR Containment and Inter-Code Comparison 6   7  
7321Final Numerical Simulation of the Restart of the Cooling System in a Storage Pool Under Boiling Conditions 6   5  
7459Draft Assessment of Fuel Damage of Pool Type Research Reactor in The Case of Fuel Plates Blockage 6   5  
7373Final Application of Fractional Scaling Analysis and Local Scaling to Design a Test Facility of IRIS Pressurizer 6.05    
7164Final Analysis of Post-LOCA Long Term Cooling Performance and Effect of Recirculation Flow 6   5  

6.06 Systems Analysis & Assessment-II
Wednesday, May 16, 2007 • 15:30-17:15
Francesco D’Auria, Università di Pisa; Dipartimento di Ingegneria, Meccanica, Nucleare e della Prodzione (DIMNP) Via Diotisalvi, 2; I-56126 Pisa, Italy; Ph: 39 050 836653 FAX: 39 050 836665 E-mail: dauria@ing.unipi.it
7116Final Evaluation of a Coolant Injection into the In-Vessel with a RCS Depressurization using SCDAP/RELAP5 5   6  
7048Final Studies on Scaled Models for Gas Entrainment in the Surge Tank of LMFBR 66    
7217Final Application of Three-Dimensional Thermal-Hydraulic Code BAGIRA for Modeling Complex Two-Phase Flows in Primary and Secondary Circuits of NPP's with VVER-1000 6    
7050Final Validation of the ATHLET System Code on Integral Experimental Facilities 6   1  

6.07 Thermal Hydraulics Measurement and Modeling Fundamentals
Wednesday, May 16, 2007 • 8:15-10:00
T. Takata, Osaka University; , ; , Japan; Ph: FAX: E-mail: takata_t@see.eng.osaka-u.ac.jp
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, ; Collage Station , TX 77843-3133 USA; Ph: 409-845-7090 FAX: 409-845-6443 E-mail: y-hassan@tamu.edu
7334Final Time Resolved Particle Image Velocimetry Measurements Inside a Packed Bed Reactor 6   2  
7170Final Characterization of TiO2 Agglomerates for the Investigation of Aerosol Behaviour in a Steam Generator Tube Rupture Event 5    
7114Final Water Level Gauging in a Bellows Tube by Combination of a Special Shoe and a Position Control System 5   4  
7480Final Operating and Mathematical Representation of Resonances between Flow Parameters Oscillations and Structure Vibrations of NPP 6    
7061Final Modification of Godunov Computation Method for Modeling Non-Stationary Gas-Liquid Flow 6    

6.08 System Simulation Models and Codes-I
Wednesday, May 16, 2007 • 13:30-15:15
Bernard Faydide, CEA; CEA/Grenoble, DEN/DER/SSTH, 17, Rue des Martyrs 38054 Grenoble Cedex 9; , France; Ph: (33) 4 38 78 40 53 FAX: (33) 4 38 78 57 28 E-mail: bernard.faydide@cea.fr
7323Final Assessment of Rod-To-Rod Thermal Radiation Heat Transfer Contribution During Reflood in PWR Fuel Assemblies 6   6  
7189Final Qualification of the 3D Thermal-Hydraulics Model of the Code System TRACE Based on Plant Data 6   5  
7086Final A New Algorithm Soar of the Coupled Solver for an Incompressible Flow 6    

6.08 System Simulation Models and Codes-II
Wednesday, May 16, 2007 • 15:30-17:15
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail: nusret.aksan@psi.ch
7551Final Development of Computational Two-phase Flow Analysis Code with Interfacial Area Transport Equation 6    
7539Final Relating System-to-CFD Coupled Code Analyses to Theoretical Framework of a Multiscale Method 6    
7363Final Development of a Versatile Plant Simulation Code with PC 6    
7314Final Recent Heat Transfer Improvements to the RELAP5-3D Code 6    

6.10 Thermal Hydraulics of BWR Systems
Wednesday, May 16, 2007 • 8:15-10:00
Francesco D’Auria, Università di Pisa; Dipartimento di Ingegneria, Meccanica, Nucleare e della Prodzione (DIMNP) Via Diotisalvi, 2; I-56126 Pisa, Italy; Ph: 39 050 836653 FAX: 39 050 836665 E-mail: dauria@ing.unipi.it
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail: nusret.aksan@psi.ch
7483Final Development and Validation of an Extended Two-Phase Computational Fluid Dynamics Model for the Analysis of Boiling Flow in Reactor Fuel Assemblies 6   1  
7276Final Thermal-Hydraulic Stability Analysis of a Natural Circulation BWRs 6   1  
7074Final Reliability Analysis of a Boiling Two-phase Natural Circulation System Using the APSRA Methodology 4   5  

6.11 Thermal Hydraulics of SCWR Systems
Tuesday, May 15, 2007 • 8:15-10:00
Nusret Aksan, Paul Scherrer Institut (PSI); Thermal-Hydraulics Laboratory, ; CH-5232 Villigen PSI , Switzerland ; Ph: 41 (0) 56 310 2710 FAX: 41 (0) 56 310 4481 E-mail: nusret.aksan@psi.ch
7271Final Prediction and Analysis of Onset of Turbulent Convective Heat Transfer Deterioration in Supercritical Water Flows 1   6  
7089Final Secondary Flows in the Cooling Channels of the High-Performance Light-Water Reactor