2006 International Congress on Advances in Nuclear Power Plants 

Embedded International Topical Meeting at the 2006 ANS Annual Meeting

ICAPP '06  •  June 4-8, 2006  •  Reno, NV  •  Reno Hilton
Home Organizers Call For Papers Papers/Program Highlights Reno/Hilton 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.

0.00: Unassigned Abstracts/Papers

1.00: Water-Cooled Reactor Programs and Issues

2.00: High Temperature Gas Cooled Reactors

3.00: Long Term Reactor Programs and Strategies

4.00: Operation, Performance & Reliability Management

5.00: Plant Safety Assessment and Regulatory Issues

6.00: Thermal Hydraulic Analysis and Testing

7.00: Core and Fuel Cycle Concepts and Experiments

8.00: Material and Structural Issues

9.00: Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications

10.00: Near Term Issues

11.00: Reactor Physics and Analysis

12.00: Space Power and Propulsion
 

Up

0.00: Unassigned Abstracts/Papers

Up

1.00: Water-Cooled Reactor Programs and Issues
Bernie Copsey, Framatome ANP; Mailstop OF-55, 3315 Old Forest Road ; Lynchburg, VA 24501 USA; Ph: 434-832-2545, 434-841-0313 FAX: 434-832-3828 E-mail: Bernie.Copsey@framatome-anp.com
Toney Mathews, Framatome ANP; 7207 IBM Drive, CLT-2B, ; Charlotte, NC 28262 USA; Ph: (704) 805-2189 FAX: (704) 805-2675 E-mail: Toney.Mathews@framatome-anp.com
Shin Whan Kim, Korea Power Engineering Company (KOPEC) ; Safety Analysis Department , 150, Duckjin-Dong, Yusong-Ku ; Taejon, 305-353 Korea; Ph: 82-42-868-8733 FAX: 82-42-861-1485 E-mail: sleepy@ns.kopec.co.kr
Hee Yong Lee, KHNP; , ; , Korea; Ph: FAX: E-mail: leehhy@khnp.co.kr
Werner Brettschuh, Framatome ANP GmbH; P.O. Box: 10 05 51, ; Offenbach , 63005 Germany; Ph: 49 69 2557 1146 FAX: 49 69 2557 1870 E-mail: Werner.Brettschuh@framatome-anp.com
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
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
Michitugu Mori, TEPCO; 4-1 Egasaki-cho, Tsurumi-ku, , ; Yokohama City , Kanagawa Prefecture 230-8510 Japan; Ph: 045-613-6701 FAX: 045-613-7899 E-mail: mori-mcy@rd.tepco.co.jp

1.01 Advanced BWRs
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
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
Robert E. Gamble, GE Nuclear Energy; M/C 365, 175 Curtner Ave. ; San Jose , CA 95125 USA; Ph: 408-925-3352 FAX: 408-925-3991 E-mail: robert.gamble@gene.ge.com
6466Cdrom Innovative-Simplified Nuclear Power Plant Efficiency Evaluation with High-Efficiency Steam Injector System 1    
6426Cdrom SWR 1000: An Advanced, Medium-Sized Boiling Water Reactor, Ready for Deployment 1.01    
6372Cdrom Design Study Status of Compact Containment BWR 1   10  
6367Cdrom ESBWR - An Evolutionary Reactor Design 1    
6280Cdrom Development of Medium Small BWR “DMS” (Double MS: Modular Simplified & Medium Small Reactor) 1    

1.02 Economics, Regulation, Licensing and Construction
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
Toney Mathews, Framatome ANP; 7207 IBM Drive, CLT-2B, ; Charlotte, NC 28262 USA; Ph: (704) 805-2189 FAX: (704) 805-2675 E-mail: Toney.Mathews@framatome-anp.com
6406Cdrom Multinational Design Approval Program 1    
6131Pres. Development of the Evaluation System of Total Modularization Effect for Power Plant Construction 1   10  
6158Cdrom From Streams to Lumps: Transforming Long-Term Incentives into Up-Front Financing for New Nuclear Construction 1    

1.03 Advanced PWRs
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
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
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
6477Cdrom IRIS - Progressing Toward a Worldwide Deployment 1.03    
6172Cdrom Advanced Design Feature of APR1400 and Realization in Shin Kori Construction Project 10   1  
6106Cdrom Development of Emergency Response Guidelines (ERGs) for AP1000 10   5  
6273Cdrom AP1000 Design for Security 1    
6044Cdrom Technology Verification of the Advanced Integral Reactor SMART 1   9  
6067Pres. European Utility Requirements (EUR) Volume 3 Assessment for AP1000 1   5  

1.04 Innovative Water Cooled Reactors
WEDNESDAY, JUNE 7, 2006 • 2:30 P.M. - 4:00 P.M.
Werner Brettschuh, Framatome ANP GmbH; P.O. Box: 10 05 51, ; Offenbach , 63005 Germany; Ph: 49 69 2557 1146 FAX: 49 69 2557 1870 E-mail: Werner.Brettschuh@framatome-anp.com
6274Cdrom Design and Dynamic Performance of a Small Water Cooled Reactor Fuelled with Plutonium in Rock-Like Oxide (ROX) Form 1    
6241Cdrom Feasibility of Improving BWR Performance Using Hydride Fuel 1    
6014Cdrom The Results of Feasibility Study of Co-Generation NPP with Innovative VK-300 Simplified Boiling Water Reactor 9   3  
6461Cdrom Overview of Integrated Modular Water Reactor (IMR) Development 1    
6460Cdrom Design of Steam Generator for 700 MWE IPHWR    

Up

2.00: High Temperature Gas Cooled Reactors
Phil MacDonald, Consultant; , ; Cedar Hill , TX USA; Ph: 972-299-9005, 208-521-1208 FAX: 208 526 2930 E-mail: pemcedarhill@yahoo.com
Bernie Copsey, Framatome ANP; Mailstop OF-55, 3315 Old Forest Road ; Lynchburg, VA 24501 USA; Ph: 434-832-2545, 434-841-0313 FAX: 434-832-3828 E-mail: Bernie.Copsey@framatome-anp.com
Lewis Lommers, Framatome ANP; 3315 Old Forest Road, P.O. Box 10935 ; Lynchburg, VA 24506 USA; Ph: 434-832-3687 FAX: 434-832-3828 E-mail: Lewis.Lommers@framatome-anp.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
Michel Lecomte, Framatome ANP; Tour AREVA, ; Paris La Defense Cedex , 92084 France; Ph: 33 147965673 FAX: 33 147961488 E-mail: michel.lecomte@areva.com
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
Shoji KATANISHI, Japan Atomic Energy Agency (JAEA); , ; Oarai-machi, Ibaraki-ken 311-1393 Japan; Ph: 81-29-266-7718 FAX: 81-29-266-7608 E-mail: katanishi.shoji@jaea.go.jp

2.01 Pebble Bed Modular Reactors
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
John M (Jack) Tuohy, Hitachi America; Power Systems Division, 50 Prospect Avenue ; Tarrytown, , NY 10591-4625 USA; Ph: 914-524-6671, 201-410-5755 Cell FAX: E-mail: tuohyj@alum.mit.edu,john.tuohy@hal.hitachi.com
Phil MacDonald, Consultant; , ; Cedar Hill , TX USA; Ph: 972-299-9005, 208-521-1208 FAX: 208 526 2930 E-mail: pemcedarhill@yahoo.com
6149Cdrom Experimental Results of Pebble Beds Thermal Hydraulic Characteristics 2    
6416Cdrom Cycle Configurations for a PBMR Steam and Electricity Production Plant 2    
6319Cdrom The Control of the PBMR Nuclear Power Unit 6   2  
6238Cdrom Selection of Licensing Basis Events for the U.S. Design Certification of the PBMR 2    

2.04 Innovative HTRs, Fuels and Materials
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Michel Lecomte, Framatome ANP; Tour AREVA, ; Paris La Defense Cedex , 92084 France; Ph: 33 147965673 FAX: 33 147961488 E-mail: michel.lecomte@areva.com
6455Cdrom High-Temperature Gas Cooled Reactors: Design Features, Potential and Challenges 2    
6201Cdrom Cermet Coatings Tribological Behavior in High Temperature Helium    
6037Cdrom RAPHAEL: The European Union’s (Very) High Temperature Reactor Project 2   3  

2.05 Heat Exchangers
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
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
6040Cdrom Multi-Scale Stress Analysis For Compact Plate Heat Exchangers 8   9  
6457Cdrom Development of the Intermediate Heat Exchanger (IHX) for ANTARES 2.06    
6357Cdrom Design of a Small Scale High Temperature Gas Loop for Process Heat Exchanger Design Tests 2   6  
6105Cdrom Heat Exchangers for the Next Generation of Nuclear Reactors 2    
6474Cdrom Design Issues Affecting Piping Associated with a New Moisture Separator Re-heater 2.05    

2.06 Power Conversion
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
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
6231Cdrom A Computational Study on Inlet Plenum Flow for a NHDD Plant 2    
6287Cdrom Thermal Assessment of Very High Temperature Reactors: Direct and Indirect Brayton Power Cycles 2   9  
6213Cdrom Evolution of the Power Conversion Unit Design of the GT-MHR 2    
6064Cdrom Operational Curves for HTGR’s Coupled to Closed Brayton Cycle Power Conversion Systems 2   6  

2.07 Modeling and Simulation of HTRs
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Lewis Lommers, Framatome ANP; 3315 Old Forest Road, P.O. Box 10935 ; Lynchburg, VA 24506 USA; Ph: 434-832-3687 FAX: 434-832-3828 E-mail: Lewis.Lommers@framatome-anp.com
Phil MacDonald, Consultant; , ; Cedar Hill , TX USA; Ph: 972-299-9005, 208-521-1208 FAX: 208 526 2930 E-mail: pemcedarhill@yahoo.com
6338Cdrom Design of an Alternative Coolant Inlet Flow Configuration for the Modular Helium Reactor 2.   6.  
6326Cdrom GT-MHR Start-up Reactivity Insertion Transient Analysis Using Simulink    
6243Cdrom Overview of Helium Cooled System Applications with RELAP at ENEA 6   2  
6218Cdrom Thermal Analysis for a Heterogeneous VHTR Disposition Element as a Function of Burnup 2    
6182Cdrom Validation of CATHARE Code for Gas-Cooled Reactors: Comparison with EVO Experimental Data on Oberhausen II Facility 2    
6472Cdrom Optimization of the Neutronics of the Advanced High Temperature Reactor 2.07    

Up

3.00: Long Term Reactor Programs and Strategies
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
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
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
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
Masakazu ICHIMIYA, Japan Atomic Energy Agency (JAEA); , ; , Japan; Ph: 81-29-267-4141 FAX: E-mail: ichimiya.masakazu@jaea.go.jp

3.01 Supercritical Pressure Water Reactors-I: General Design/Materials
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 2:30 P.M.
Hussam Khartabil, AECL; , ; , Canada; Ph: FAX: E-mail: khartabilh@aecl.ca
Thomas Schulenberg, FZK/IKET; Institute for Nuclear and Energy Technologies (IKET), Forschungszentrum Karlsruhe ; Karlsruhe, D-76021 Germany; Ph: 49 7248 82 3450 FAX: 49 7247 82 4837 E-mail: thomas.schulenberg@iket.fzk.de
6229Cdrom Mechanical Analysis of the Assembly Box of a HPLWR Fuel Assembly 3    
6224Cdrom Static Thermal Design Limit of Supercritical Water-Cooled Fast Reactor 3   6  
6098Cdrom Conceptual Design of a Reactor Pressure Vessel and its Internals for a HPLWR 3    
6190Cdrom In-situ Measurements of the Oxidation of AISI 316L(NG) and its Constituents (Fe,Cr and Ni) in Ultrasupercritical Water 3    

3.02 Supercritical Pressure Water Reactors-II: R&D Programs/Stability
WEDNESDAY, JUNE 7, 2006 • 2:30 P.M. - 4:00 P.M.
Katsumi Yamada, Toshiba Corporation / Isogo Nuclear Engineering Center; 8, Shin-Sugita-cho, Isogo-ku ; Yokohama , Kanagawa Prefecture 235-8523 Japan; Ph: 81-45-770-2155 FAX: 81-45-770-2298 E-mail: katsumi4.yamada@toshiba.co.jp
Hussam Khartabil, AECL; , ; , Canada; Ph: FAX: E-mail: khartabilh@aecl.ca
6022Cdrom R&D on Supercritical Pressure Water-Cooled Reactor in Korea 3.01    
6353Cdrom Research Program of a Super Fast Reactor 3   1  
6227Cdrom Flow Stability of Supercritical Water Cooled Systems 3    
6424Cdrom Coupled Neutronic-Thermal Hydraulic Out-of-Phase Stability of Supercritical Water Cooled Reactors 3    

3.03 Supercritical Pressure Water Reactors-III: Thermal Hydraulics
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
Slawomir (Mike) Modro, INL; P.O. Box 1625, ; Idaho Falls , Idaho 83415-3855 USA; Ph: 208-526-9402 FAX: E-mail: m.modro@iaea.org
Yoon-Yeong Bae, KAERI; 150 Deokjin Yuseong, ; Daejeon, 305-353 Korea; Ph: 82-42-868-8130 FAX: 82-42-868-8990 E-mail: yybae@kaeri.re.kr
6123Cdrom Experimental Investigation on Heat Transfer Characteristics in Vertical Upward Flow of Supercritical CO2 3   6  
6211Cdrom Prediction of Heat Transfer for a Supercritical Water Test with a Four Pin Fuel Bundle 3    
6246Cdrom Development of Mechanistic Modeling Capabilities for Generation-IV Supercritical Water-Cooled Reactor (SCWR) 3    
6325Cdrom Heat Transfer Measurements in the University of Wisconsin Supercritical Water Loop 3.01    
6334Cdrom Numerical Study of Heat Transfer in Supercritical Pressure Water in Tight Fuel Rod Channels 3.01    

3.04 Lead-alloy Fast Reactors-I: Heavy Liquid Metal Cooled Fast Reactors
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
Luciano Cinotti, Ansaldo Nucleare; Corso F. M. Perrone, 25, ; Genoa , 16161 Italy; Ph: 39 010 655 8283 FAX: 39 010 655 8400 E-mail: cinotti@ansaldo.it
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
6242Cdrom Effect of Fuel Type on the Attainable Power of the Encapsulated Nuclear Heat Source Reactor 3    
6148Cdrom Optimized Battery-Type Reactor Primary System Design Utilizing Lead 3    
6023Cdrom Use of Multi-Purpose Modular Fast Reactors SVBR-75/100 in Market Conditions 3    
6008Cdrom A CANDU-Based Fast Irradiation Reactor 9   3  

3.04 Lead-alloy Fast Reactors-II: Lead-alloy Coolant Technology and Thermal Hydraulics
WEDNESDAY, JUNE 7, 2006 • 2:30 P.M. - 4:00 P.M.
James J. Sienicki, ANL; , ; , USA; Ph: FAX: E-mail: sienicki@anl.gov
Ning Li, MIT; , ; , ; Ph: FAX: E-mail: ningli@MIT.EDU
Kune Y. Suh, Seoul National University (SNU); Department of Nuclear Engineering, San 56-1 Sillim-Dong Kwanak-Gu; Seoul, 151-742 Korea; Ph: 82-2-880-8324 FAX: 82-2-889-2688 E-mail: kysuh@snu.ac.kr
6173Cdrom Pre-Test Analysis of the MEGAPIE Spallation Source Target Cooling Loop Using TRAC/AAA Code 3   6  
6146Cdrom Natural Convection Heat Transfer Characteristics of Liquid Metal Cooled by Subcooled Water 3    
6303Cdrom Performance of Magnetic Hydro-Dynamic Pump in Lead-Bismuth Eutectic Target Circuit (TC-1)    
6277Cdrom Heavy Liquid Metal Technologies Development in KALLA 3   6  
6284Cdrom Operation Experience of LBE Loop: HELIOS 3    

3.05 Sodium Fast Reactors
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Satoru Kondo, JAEA; Advenced Nuclear System R&D Directorate, 1 Shiraki ; Tsuruga-shi, Fukui-ken 919-1279 Japan; Ph: 81-770-39-1031 FAX: 81-770-39-9103 E-mail: kondo.satoru@jaea.go.jp
Philippe Dufour , CEA; , ; , France; Ph: FAX: E-mail: philippe.dufour@cea.fr
6076Cdrom A Modular Metal Fuel Fast Reactor Enhancing Economic Potential 3   9  
6255Cdrom Sensitivity and Uncertainty Analysis of ARGO-3 Code on the ULOF Event of the 4S Reactor 3   5  
6359Cdrom Flow and Temperature Distributions Evaluation on Sodium Heated Large Sized Straight Double-wall-tube Steam Generator 3   6  
6411Final Technology Options for a Fast Spectrum Test Reactor 3   7  

3.06 Gas Fast Reactors
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Tom Wei, ANL; , ; , ; Ph: FAX: E-mail: tycwei@anl.gov
Jean-Claude Garnier, CEA; , ; , France; Ph: FAX: E-mail: jean-claude.garnier@cea.fr
6311Cdrom GCFR: The European Union’s Gas Cooled Fast Reactor Project 3    
6312Cdrom Comparative Transient Analysis of Gas-cooled Fast Reactor for Different Fuel Types 2   5  
6147Cdrom Contribution to GFR Design Option Selection 3   2  
6125Cdrom Plant System Design of Supercritical CO2 Direct Cycle Gas Turbine Fast Reactor 3    
6097Cdrom Shutdown/Emergency Cooling System for a 2400 MWth Supercritical CO2-Cooled Direct-Cycle GFR 3    
6041Cdrom High Temperature Helium -Cooled Fast Reactor (HTHFR) 2    

3.07 Liquid-Salt-Cooled High-Temperature Reactors-I
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Per Peterson, UC-Berkeley; 4111 Etcheverry Hall, ; Berkeley, CA 94720-1730 USA; Ph: (510) 643-7749 FAX: (510) 643-9685 E-mail: peterson@nuc.berkeley.edu
Dan Ingersoll, ORNL; P. O. Box 2008, MS-6162, ; Oak Ridge, TN 37831-6162 USA; Ph: 865-574-6102 FAX: 865-574-7879 E-mail: ingersolldt@ornl.gov
6264Cdrom Overview and Status of the Advanced High-Temperature Reactor 3    
6464Cdrom Effects of Coolant Temperature Changes on Reactivity for Various Coolants in a Liquid Salt Cooled Very High Temperature Reactor (LS-VHTR) 3.07    
6244Cdrom Investigation of an Alternative Fuel Form for the Liquid Salt Very High Temperature Reactor (LS-VHTR) 3    
6160Cdrom Salt Selection for the LS-VHTR 03   03  

3.08 Liquid-Salt-Cooled High-Temperature Reactors-II
THURSDAY, JUNE 8, 2006 • 1:00 P.M. - 3:00 P.M.
Dan Ingersoll, ORNL; P. O. Box 2008, MS-6162, ; Oak Ridge, TN 37831-6162 USA; Ph: 865-574-6102 FAX: 865-574-7879 E-mail: ingersolldt@ornl.gov
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
6055Cdrom Alternative Passive Decay-Heat Systems for the Advanced High-Temperature Reactor 3    
6052Cdrom A Flexible Base-Line Design for the Advanced High-Temperature Reactor Utilizing Metallic Reactor Internals (AHTR-MI) 3   9  
6086Cdrom Performance of Decay Heat Removal Systems in the LS-VHTR 3   5  
6208Cdrom Thermal-Hydraulic Analyses of the LS-VHTR 3    
6159Cdrom Dynamic System Model of the LS-VHTR to Estimate Design Parameter Impacts on Safety Margin and Reactor Economics 3    

3.09 Liquid-Salt-Cooled and Molten-Salt Reactors-III
THURSDAY, JUNE 8, 2006 • 3:00 P.M. - 5:00 P.M.
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
Per Peterson, UC-Berkeley; 4111 Etcheverry Hall, ; Berkeley, CA 94720-1730 USA; Ph: (510) 643-7749 FAX: (510) 643-9685 E-mail: peterson@nuc.berkeley.edu
6132Cdrom Fast Thorium Molten Salt Reactors Started with Plutonium 3    
6295Cdrom Molten Salt Reactor Technology Gaps 3.07    
6002Cdrom Experience with Alloys Compatibility with Fuel and Coolant Salts and their Application to Molten Salt Actinide Recycler & Transmuter 3.04    
6344Cdrom Dynamics of Molten Salt Reactor 11   7  

3.10 Advanced Power Conversion Systems-I
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Per Peterson, UC-Berkeley; 4111 Etcheverry Hall, ; Berkeley, CA 94720-1730 USA; Ph: (510) 643-7749 FAX: (510) 643-9685 E-mail: peterson@nuc.berkeley.edu
6307Cdrom A Supercritical CO2 Cycle - a Promising Power Conversion System for Generation IV Reactors 3.10    
6074Cdrom Automatic Control Strategy Development for the Supercritical CO2 Brayton Cycle for LFR Autonomous Load Following 3   2  
6265Cdrom Fast Reactor with Indirect Cycle System of Supercritical CO2 Gas Turbine Plant 3    
6051Cdrom Low-Temperature Multiple-Reheat Closed Gas Power Cycles for the AHTR and LSFR 3   9  

3.10 Advanced Power Conversion Systems-II
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
Haihua Zhao, UC-Berkeley; , ; , ; Ph: FAX: E-mail: zhaohh@berkeley.edu
6369Cdrom Capsule Test for Investigating Sodium- Carbon Dioxide Interaction 3    
6094Cdrom Design of Turbomachinery for the Supercritical CO2 Gas Turbine Fast Reactor 3   9  
6142Cdrom Supercritical Carbon Dioxide Brayton Power Conversion Cycle Design for Optimized Battery-Type Integral Reactor System 3    

3.11 Status of Advanced Reactor Programs
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Hiroshi Sekimoto, Tokyo Institute of Technology; , ; , Japan; Ph: FAX: E-mail: hsekimot@nr.titech.ac.jp
Theron Marshall, INL; , ; , USA; Ph: FAX: E-mail: Theron.Marshall@inl.gov
6432Cdrom The IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO): Study on Opportunities and Challenges of Large-Scale Nuclear Energy Development    
6329Cdrom Assessment of a French Scenario with the INPRO Methodology 3    
6292Cdrom Developments in Molten Salt and Liquid-Salt-Cooled Reactors    
6285Cdrom R&D Trends for the Future Sodium Fast Reactors in France 3    

3.12 International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)-Panel
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
Atam Rao, IAEA; Wagrammer Strasse 5, PO Box 200 ; A-1400 Vienna, Austria; Ph: 43 1 2600 22808 FAX: E-mail: a.rao@iaea.org

Up

4.00: Operation, Performance & Reliability Management
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
Byung-sik Lee, KHNP; , ; , Korea; Ph: 82 51 726 2290, cell: 82 10 4693 6137 FAX: E-mail: leeb@khnp.co.kr
Laurent Delabroy, EDF-DPN; , ; , France; Ph: FAX: E-mail: laurent.delabroy@edf.fr
Yoichiro Shimazu, Hokkaido University; Division of Quantum Energy Engineering, Graduate School of Engineering, Hokkaido University Kita 13, Nishi 8; Sapporo , Hokkaido 060-8628 Japan; Ph: 81-11-706-6676 FAX: 81-11-706-7888 E-mail: shimazu@qe.eng.hokudai.ac.jp

4.01 Performance and Condition Monitoring and Predictive Modeling-I
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Thomas E. Blue, Ohio State Univ; Department of Mechanical Engr., Nuclear Engr. Program, Suite 255 650 Ackerman Road; Columbus , OH 43202 USA; Ph: 614-292-0629 FAX: 614-292-3163 E-mail: blue.1@osu.edu
6260Cdrom A Flow-rate Measurement Method by Using the Motor Power of the Axial Flow Pumps with Higher Specific-speeds 4    
6237Cdrom Fault Diagnosis of Steam Generator Using Signed Directed Graph and Artificial Neural Networks    
6316Cdrom Predictions of Displacement Damage and Count Rate for SiC Detectors in IRIS 11   1  
6053Cdrom Gas Release Driven Dynamics in Research Reactors Piping 6   4  

4.01 Performance and Condition Monitoring and Predictive Modeling-II
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
Yoichiro Shimazu, Hokkaido University; Division of Quantum Energy Engineering, Graduate School of Engineering, Hokkaido University Kita 13, Nishi 8; Sapporo , Hokkaido 060-8628 Japan; Ph: 81-11-706-6676 FAX: 81-11-706-7888 E-mail: shimazu@qe.eng.hokudai.ac.jp
Ed Dugan, Univ of Florida; 202 NSC, Box 118300, Nuclear & Radiological Engineering University of Florida; Gainesville, FL 32611 USA; Ph: (352) 392 1401 FAX: (352) 392 3380 E-mail: edugan@ufl.edu
6347Cdrom Preliminary Measurements Supporting Reactor Vessel and Large Component Inspection Using X-Ray Backscatter Radiography by Selective Detection 4    
6047Cdrom Day, Night and All-Weather Security Surveillance Automation 5   4  
6192Cdrom A System for Water Thickness Gaging in a Bellows Tube was Developed, using Special UT Probe Attachment and an Immersion Ultrasonic Inspection 4    
6321Cdrom Inspection Head Design for the In-Service Inspection of Fuel Channels of Pressurized Heavy Water Reactors 4   5  

4.03 Instrumentation and Control Upgrades, Decisions and Reliability-I
THURSDAY, JUNE 8, 2006 • 1:00 P.M. - 3:00 P.M.
Tricia Bolian, AREVA; 1345 Ridgeland Parkway, Suite 130, ; Alpharetta , GA 30004 USA; Ph: 770-225-9604 FAX: 770-225-9601 E-mail: Tricia.Bolian@areva.com
6210Cdrom Plant Modernization with Digital Reactor Protection System: Safety System Upgrades at US Nuclear Power Stations 4    
6226Cdrom Design of the Fully Digitalized SOE System in Nuclear Power Plants 4    
6152Cdrom Experience with Control Systems Modernization on Operating Nuclear Units (Kozloduy NPP VVER 1000) 4   5  
6015Cdrom Application of Digital Technology for the Plant Protection System in Ulchin Nuclear Power Plant Units 5&6 1   4  

4.03 Instrumentation and Control Upgrades, Decisions and Reliability-II
THURSDAY, JUNE 8, 2006 • 3:00 P.M. - 5:00 P.M.
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
Laurent Delabroy, EDF-DPN; , ; , France; Ph: FAX: E-mail: laurent.delabroy@edf.fr
6346Cdrom Accumulation of Operational History through Emulation Test to Meet Proven Technology Requirement for Newly Developed I&C Technology 4    
6221Cdrom An Evaluation System for Checking the Status of I&C Systems in Nuclear Power Plants 4    
6128Cdrom Plant Maintenance and Improvement Experiences for Control System in UCN 5&6 4   5  
6342Cdrom Use Case Driven Approach to Develop Simulation Model of PCS for APR1400 Simulator 4   5  
6469Cdrom Parallel Magnetic Flow Electromagnet for Movable Coil Control-rod Driving Mechanism 4032    

4.04 Availability, Preventive Maintenance, Optimization and Best Practices-I
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 2:30 P.M.
César Queral, Universidad Politécnica de Madrid; Rios Rosas 21, ; Madrid, 28003 Spain; Ph: 34913367061 FAX: 3491336 69 72 E-mail: cesar@dse.upm.es
Seth A Swamy, Westinghouse; , ; , USA; Ph: FAX: E-mail: swamysa@westinghouse.com
6378Cdrom A Flaw Tolerance Approach to Address Reactor Vessel Head Penetration Cracking Issue 4    
6240Cdrom Application of a Software Tool for Evaluating Human Factors in Accident Sequences 5    
6072Cdrom Interdisciplinary Approach to Reduce Human Errors in the Nuclear Power Plant 4   3  
6340Cdrom The Status of Plant Lifetime Management Study of Wolsong Unit 1 in Korea 4   5  

4.04 Availability, Preventive Maintenance, Optimization and Best Practices-II
WEDNESDAY, JUNE 7, 2006 • 2:30 P.M. - 4:00 P.M.
César Queral, Universidad Politécnica de Madrid; Rios Rosas 21, ; Madrid, 28003 Spain; Ph: 34913367061 FAX: 3491336 69 72 E-mail: cesar@dse.upm.es
Seth A Swamy, Westinghouse; , ; , USA; Ph: FAX: E-mail: swamysa@westinghouse.com
6348Cdrom Lessons Learnt from Seismic PRA and Margin Assessments for New Nuclear Power Plants 4   5  
6333Cdrom Development of Performance Demonstration Programs for Steam Generator Tubing Analysts in Korea 4    
6114Cdrom Current Status of Continued Operation for Kori unit 1 beyond Design Life 4   5  
6318Cdrom US EPR - Tests Performed to Confirm the Mechanical and Hydraulic Design of the Vessel Internals    

4.05 Economic Decisions, Software Solutions, Organization and Work Management
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
James K. Liming, ABSG Consulting; 300 Commerce Drive, Suite 200 ; Irvine , CA 92602-1305 USA; Ph: 714-734-2540 FAX: 714-734-4282 E-mail: jliming@absconsulting.com
Liu Fei, Harbin Engineering Univ; Nuclear Power Simulation Research Center of Harbin Engineering, ; Harbin, Heilongjiang, P.R. 150001 China; Ph: 86-451-82569302 FAX: 86-451-82569611 E-mail: liufei@hrbeu.edu.cn
6332Cdrom Operating Cost Reduction from Large Bore Snubber Reduction/Elimination 4    
6309Cdrom Advancements in Risk-Informed Performance-Based Asset Management for Commercial Nuclear Power Plants 4   5  
6036Cdrom Study of On-line Computerized Procedure System for Nuclear Power Plant 4    

4.06 Digital Control Systems
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Steve Yang, HF Controls Corporation; 16650 Westgrove Drive, Suite #500, ; Addison, Texas 75001 USA; Ph: (972)367-4643 FAX: (972)367-4699 E-mail: steve.yang@hfcontrols.com
6434Cdrom Real-Time Graphic Display Utility For Nuclear Safety Applications 10   5  
6196Cdrom An Advanced Tool for Control System Design and Maintenance 4    
6193Cdrom Design for a New Signals Analyzer through a Circuit Modeling Simulation as a One Body System for SAC's 4    
6463Cdrom HFC-6000 for Nuclear I&C Upgrade 4   5  

4.08 The Role of Nuclear In Energy Forecasting Projections-U.S. and World
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 2:30 P.M.
Edward Quinn, ANS Past President, Longenecker and Associates; 23292 Pompeii Drive, ; Dana Point , CA 92629 USA; Ph: (949) 632-1369 FAX: E-mail: tedquinn@cox.net,Ted.L.Quinn@ips.invensys.com
6483Cdrom Prospective of the Electrical Mexican Sector: 2005-2014 4.08    
6475Cdrom Economic Analysis of the Levelized Cost of Electricity Generation 4.08    
6467Pres. Nuclear Power's Prospects: A view to 2030 4.08    
6478Pres. When Do Commercial Reactors Shut Down? The Record Since 1999 4.08    

4.09 Industry Initiatives to Manage the Impacts of Materials Aging Degradation-Panel
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Michael A. Burke, Westinghouse; , ; , USA; Ph: FAX: E-mail: burkema@westinghouse.com

Up

5.00: Plant Safety Assessment and Regulatory Issues
Nam Dinh, Royal Institute of Technology in Stockholm; , ; , Sweden; Ph: 46 8 790 9255 FAX: E-mail: nam.dinh@energy.kth.se
Sandra Sloan, Framatome ANP; , ; , USA; Ph: FAX: E-mail: Sandra.Sloan@framatome-anp.com
Youn-won Park, KINS; , ; , Korea; Ph: FAX: E-mail: k077pyw@kins.re.kr
Sun-Koo Kang, KOPEC; Integrated Safety Assessment Group, KOPEC, 360-9, Mabuk-ri, Guseong-eup ; Yongin-si, Gyeonggi-do 449-713 Korea; Ph: 82-31-284-4136 FAX: 82-31-289-4299 E-mail: skang@kopec.co.kr
JinHo Song, Korea Atomic Energy Research Institute; Thermal-Hydraulics and Reactor Safety Team, P.O. Box 105 ; Yuseong, Taejon, 305-600 Korea; Ph: 82-42-868-2850 FAX: 82-42-861-2574 E-mail: dosa@kaeri.re.kr
Christian Clément, EDF; , ; , France; Ph: FAX: E-mail: christian.clement@edf.fr
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
Akio Tsuji, Hitachi Ltd; , ; , Japan; Ph: FAX: E-mail: akio.tsuji.gc@hitachi.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 and non-LOCA - Analysis Methodologies
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 3:00 P.M.
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
Audrius Jasiulevicius, PSI; , ; , Switzerland; Ph: FAX: E-mail: audrius.jasiulevicius@psi.ch
Eckhard Krepper, FZR; , ; , Germany; Ph: FAX: E-mail: E.Krepper@fz-rossendorf.de
6371Cdrom APR1400 Reactivity Insertion Accident Analysis Using KNAP 5    
6257Cdrom Notes on the Implementation of Non-parametric Statistics within the Westinghouse Realistic Large Break LOCA Evaluation Model (ASTRUM) 6    
6212Cdrom Application of Advanced Thermal Hydraulic TRACG Model to Preserve Operating Margins in BWRs at Extended Power Uprate Conditions 5   6  
6111Cdrom RIA Limits Based on Commercial PWR Core Response to RIA 5   5  
6093Cdrom A Methodology for the Quantification of Uncertainty in Best Estimate Code Physical Models 6   5  
6031Cdrom The Improvement of the Interfacial Drag Model in RELAP5/MOD3.3 to Simulate Downcomer Boiling Phenomena in APR1400 5.01    

5.02 LOCA and non-LOCA - Plant Analyses-I
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
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
Audrius Jasiulevicius, PSI; , ; , Switzerland; Ph: FAX: E-mail: audrius.jasiulevicius@psi.ch
Sandra Sloan, Framatome ANP; , ; , USA; Ph: FAX: E-mail: Sandra.Sloan@framatome-anp.com
6078Cdrom The Evaluation of Steam Generator Level Measurement Model for OPR1000 Using RETRAN-3D 5   4  
6028Cdrom A Parametric Study of a Large Break in Reactor Inlet Header of CANDU 6 Reactors Using RELAP5 Code 5    
6239Cdrom Simulation of Loss of RHRS Sequences in the Almaraz NPP during Midloop Operation Using TRACE Code 5    
6443Cdrom Effect of Flow Configurations on Velocity and Temperature Distribution of Moderator inside 540 MWe PHWR Calandria using CFD Techniques    
6448Cdrom Assessment of Shutdown Systems Performance for LBLOCA for TAPS 3&4 5    
6419Cdrom Effect of Reactor Channel Modelling On Rewetting Pattern for AHWR Fuel Cluster 5   6  

5.02 LOCA and non-LOCA - Plant Analyses-II
THURSDAY, JUNE 8, 2006 • 1:00 P.M. - 3:00 P.M.
Sandra Sloan, Framatome ANP; , ; , USA; Ph: FAX: E-mail: Sandra.Sloan@framatome-anp.com
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
Audrius Jasiulevicius, PSI; , ; , Switzerland; Ph: FAX: E-mail: audrius.jasiulevicius@psi.ch
6217Cdrom AREVA Team Develops Sump Strainer Blockage Solution for PWRs 5    
6376Cdrom LOCA Feasibility Study of Almaraz NPP 110% Power Uprate 5.02    
6096Cdrom Fuel and Core Design Verification for Extended Power Uprate in Ringhals Unit 3 5   11  
6429Cdrom Process Control Logic Modification to Mitigate Transient Following Tripping of a Primary Circulating Pump for a 540 MWe PHWR Power Plant 5    
6444Cdrom Assessment of Heat up of Shut-off rods of 540MWe IPHWRs using CFD Techniques    
6447Cdrom LOCA Analysis for Assessment of Stagnation Feeder Break Size for TAPS 3&4 5    
6453Cdrom Plant Transient Analysis for TAPS-3&4 using RELAP-5/MOD 3.2 5    

5.03 Advances in Severe Accident Analysis and Management
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 3:00 P.M.
Tim Haste, PSI; Paul Scherrer Institute, ; 5232 Villigen PSI, 5232 Switzerland; Ph: 41 56 310 27 64 FAX: 41 56 310 44 81 E-mail: tim.haste@psi.ch
Sudhamay Basu, US NRC; Office of Nuclear Regulatory Research, Mail Stop T-10F13A 11545 Rockville Pike; Rockville, MD 20852 USA; Ph: 301 415 6774 FAX: 301 415 5160 E-mail: sxb2@nrc.gov
6300Cdrom SARNET: Integrating Severe Accident Research in Europe - Safety Issues in the Source Term Area 5    
6091Cdrom Detailed Analysis of In-Vessel Melt Progression in the Loss of Coolant Accident of OPR1000 5    
6266Cdrom IAEA Activities in the Area of Safety Analysis and Accident Management 5    
6382Cdrom OSSA - An Optimized Approach to Severe Accident Management: EPR Application 5    
6438Cdrom Accident Management for Indian Pressurized Heavy Water Reactors 5    
6081Cdrom CANDU Severe Accident Analysis 6   5  

5.04 Severe Accident Phenomena: Experiments and Modeling-I
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
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
Sevostian Bechta, NITI; Division of Severe Accident Research, ; Sosnovy Bor, Leningrad region 188540 Russia; Ph: 7 81369 22064 FAX: 7 81369 23672 E-mail: bechta@sbor.spb.su
6330Cdrom Use of Molten Core Concrete Interactions in the Melt Stabilization Strategy of the EPR 5   5  
6200Cdrom Simulation of Molten Core Concrete Interaction in Oxide/Metal Configuration with the TOLBIAC-ICB Code: Application to the BETA Experiments 5.07    
6199Cdrom Assessment of Two-Phase Flow Heat Transfer Correlations for Molten Core Concrete Interaction Study 5.07    
6165Cdrom Phenomenological Modeling of the Melt Eruption Cooling Mechanism During Molten Core-concrete Interaction (MCCI) 5   6  

5.05 Severe Accident Phenomena: Experiments and Modeling-II
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 2:30 P.M.
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
Sergei Petoukhov, Atomic Energy of Canada Limited (AECL) ; Fuel & Fuel Channel Safety Branch, Stn. 88 , Chalk River Laboratories Atomic Energy of Canada Limited ; Chalk River , Ontario K0J 1J0 Canada; Ph: (613)584-8811 ext.4361 FAX: (613)584-8220 E-mail: petoukhovs@aecl.ca
6164Cdrom The Results of the CCI-3 Reactor Material Experiment Investigating 2-D Core-concrete Interaction and Debris Coolability with a Siliceous Concrete Crucible 5   6  
6175Cdrom Validation of the COMET Bottom-flooding Core-catcher with Prototypic Corium 5   6  
6220Cdrom Results of the Triggered TROI Steam Explosion Experiments with a Narrow Interaction Vessel    

5.05 Severe Accident Phenomena: Experiments and Modeling-III
WEDNESDAY, JUNE 7, 2006 • 2:30 P.M. - 4:00 P.M.
Sergei Petoukhov, Atomic Energy of Canada Limited (AECL) ; Fuel & Fuel Channel Safety Branch, Stn. 88 , Chalk River Laboratories Atomic Energy of Canada Limited ; Chalk River , Ontario K0J 1J0 Canada; Ph: (613)584-8811 ext.4361 FAX: (613)584-8220 E-mail: petoukhovs@aecl.ca
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
6013Cdrom The Results From the First High-Pressure Melt Ejection Test Completed in the Molten Fuel Moderator Interaction Facility at Chalk River Laboratories 5   3  
6034Cdrom ARTEMIS Program: Investigation of MCCI by Means of Simulating Material Experiments 6    
6035Cdrom Molten Corium Concrete Interaction: Post-Calculations of 1D ARTEMIS Tests with The TOLBIAC-ICB Code 6    
6054Cdrom Experimental Study of Interactions Between Suboxidized Corium and Reactor Vessel Steel 5    

5.07 Containment Performance and Hydrogen Control
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Christian Clément, EDF; , ; , France; Ph: FAX: E-mail: christian.clement@edf.fr
6079Cdrom In-containment Thermal Hydraulic and Aerosol Behaviour during Severe Accidents: Analysis of the PHEBUS-FPT2 Experiment 5   6  
6027Cdrom On the Fission Products Transport Modeling 5    
6117Cdrom Experimental Study on the Applicability of Quenching Mesh for an Equipment Protection during a Hydrogen Combustion 5   6  
6449Cdrom Effect of Forced Mixing & Condensation on Hydrogen Distribution During Postulated Accident in MAPS Containment 5    
6450Cdrom Estimation of Source Term for Indian PHWRs (KAPS) as Part of PSA Level-2 Study 5    

5.08 Development and Application of Severe Accident Analysis Code
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
Karen Vierow, Purdue University ; School of Nuclear Engineering , 1290 Nuclear Engineering Bldg. ; West Lafayette, IN 47907-1290 USA; Ph: 1-765-494-5746 FAX: 1-765-494-9570 E-mail: vierow@ecn.purdue.edu
Hho Jung Kim, KINS; Korea Institute of Nuclear Safety, 19 Kusong-dong, Yusong-ku ; Taejon, Korea; Ph: 82-42-868-0230 FAX: 82-42-861-9945 E-mail: kimhj@kins.re.kr
6462Cdrom CANDU 6 Severe Core Damage Accident Consequence Analysis for Steam Generator Tube Rupture Scenario Using MAAP4-CANDU v4.0.5A: Preliminary Results 5    
6439Cdrom SOCRAT - The System of Codes for Realistic Analysis of Severe Accidents 5    
6420Cdrom Severe Accident Analysis for PHEBUS FPT0 Experiment with Code ICARE2 5   nil  
6301Cdrom MELCOR Simulation of the TMI-2 Severe Accident and Initial Recovery Phases 5    
6174Cdrom Application of RELAP5/SCDAP and COCOSYS Codes for Severe Accident Analysis in RBMK-1500 Reactor 5    
6026Cdrom Performance of RELAP/SCDAPSIM Code on the Fission Products Transport Prediction 5    

5.09 PRA and Risk-informed Decision Making: Methodology and Advances in Practice
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Young G. Jo, Southern Nuclear Operating Company; , ; , USA; Ph: (205)992-7305 FAX: (205) 992-7885 E-mail: YGJO@southernco.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
6009Cdrom A Formal Integration of the Decoupled Level 1 and 2 PSA Models into a Single Operational Model for Risk-informed Applications 5    
6248Cdrom A Study on the Reactor Core Failure Thresholds to Safety Operation of LMFBR    
6276Cdrom Seabrook Level 2 PRA Update to Include Accident Management 5    
6203Cdrom A Study on Structured Simulation Framework for Design and Evaluation of Human-machine Interface System: Application for On-line Risk Monitoring for Nuclear Power Plant    
6293Cdrom Reliability Assessment of SMART Reactor Protection System 5   4  
6216Cdrom Development and Verification of a SAPHIRE Risk Monitor for Chernobyl Type Reactors 5    
6451Cdrom Level-2 Probabilistic Safety Assessment for 220 MWe Indian PHWR (KAPS) 5    

Up

6.00: Thermal Hydraulic Analysis and Testing
Pradip Saha, GE Energy - Nuclear; 3901 Castle Hayne Road, M/C L60 ; Wilmington, NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail: pradip.saha@ge.com
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
Won-Pil Beak, KAERI; , ; , Korea; Ph: FAX: E-mail: wpbaek@kaeri.re.kr
Bernard Faydide, CEA; , ; , France; Ph: FAX: 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
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
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

6.01 Advances in Two-Phase Flow & Heat Transfer-I
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
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
Pradip Saha, GE Energy - Nuclear; 3901 Castle Hayne Road, M/C L60 ; Wilmington, NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail: pradip.saha@ge.com
6063Cdrom A Study on Bubble Departure and Bubble Lift-Off in Sub-Cooled Nucleate Boiling Flows 6    
6083Cdrom Heat Transfer For Subcooled Flow Boiling In Hypervapotron Configuration 6   1  
6016Cdrom Riemann Problem when Modeling Dual-Speed Bubble Flow 6    
6122Cdrom Azimuthal Film Boiling Heat Transfer from Downward-facing Hemispheres 6    
6418Cdrom Transient Response of a Natural Convection System 6   5  

6.02 Advances in Two-Phase Flow & Heat Transfer-II
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Pradip Saha, GE Energy - Nuclear; 3901 Castle Hayne Road, M/C L60 ; Wilmington, NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail: pradip.saha@ge.com
6223Cdrom Experiment Study on the Condensation Heat Transfer with Accumulated Noncondensable Gas in a Vertical Tube 6    
6032Cdrom Application of a Generalized Diffusion Layer Theory to Predict Experiment Data on Condensation of Vapor-air Mixtures 6    
6145Cdrom Preparation and Characterization of Water-Based Nanofluids for Nuclear Applications 6   1  
6005Cdrom Study of Two-phase Heat Transfer in Nanofluids for Nuclear Applications 6   1  
6305Cdrom Corrosion and Precipitation in Non-isothermal LBE Pipe/Loop Systems 3   6  

6.03 Advances in CHF and Rod Bundle Thermal Hydraulics
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 3:00 P.M.
Floyd Dunn, ANL; 9700 South Cass Ave., Bldg 208, ; Argonne, IL 60439 USA; Ph: (630) 252-4692 FAX: (630) 252-4500 E-mail: fedunn@anl.gov
6169Cdrom Development of Analytical Procedures on Two-Phase Flow in Tight-Lattice Fuel Bundles for Fast-Spectrum Light Water Reactor for Flexible Fuel Cycle (FLWR) 6    
6364Cdrom Whole Core Sub-Channel Analysis Verification With the EBR-II SHRT-17 Test 6   2  
6298Cdrom Impact of Different Correlations on TRACEv4.160 Predicted Critical Heat Flux 6    
6289Cdrom Dryout of BWR Fuel Elements    
6184Cdrom Feasibility Study on Thermal/Hydraulic Performance of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) 6    

6.04 CFD Applications to Water, Liquid Metal, and Gas Reactors-I
THURSDAY, JUNE 8, 2006 • 1:00 P.M. - 3:00 P.M.
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
Ji-Hwan Jeong, Pusan National Univ; School of Mechanical Engineering, Jangjeon-dong, Geumjeong-gu ; Busan, 609-735 Korea; Ph: 82-51-510-3050 FAX: 82-51-512-5236 E-mail: jihwan@pusan.ac.kr
6324Cdrom Large Eddy Simulation of a Mixing-T Experiment 6    
6259Cdrom Assessment of CFD Modelling for PTS Thermal-hydraulics Using Multiple Scale Experimental Facilities 6   5  
6155Cdrom On the Application of CFD Modeling for the Prediction of the Degree of Mixing in a PWR during a Boron Dilution Transient 6   5  
6048Cdrom Head Loss Evaluation in a PWR Reactor Vessel Using CFD Analysis 6   5  
6427Cdrom Case Study for Predicting Hydraulic Effects on External Ultrasonic Flowmeters 6    

6.04 CFD Applications to Water, Liquid Metal, and Gas Reactors-II
THURSDAY, JUNE 8, 2006 • 3:00 P.M. - 5:00 P.M.
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
Ji-Hwan Jeong, Pusan National Univ; School of Mechanical Engineering, Jangjeon-dong, Geumjeong-gu ; Busan, 609-735 Korea; Ph: 82-51-510-3050 FAX: 82-51-512-5236 E-mail: jihwan@pusan.ac.kr
6304Cdrom CFD Modeling of High Temperature Gas Cooled Reactors 6    
6261Cdrom Towards CFD Modelling of Critical Heat Flux in Fuel Rod Bundles 6    
6409Cdrom Study on the Gas Entrainment Design Method by CFD Data on Steady Cylindrical Systems for a Sodium-cooled Reactor 6.03   3.05  
6059Cdrom Simulation of Containment Atmosphere Mixing and Stratification Experiment in the ThAI Facility with a CFD Code 6    
6310Cdrom Progress on the Development of Two-Dimension Eulerian-Lagrangian Code LeFIX 6    

6.05 Separate Effects Thermal Hydraulic Experiments & Analysis-I
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
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; , ; , France; Ph: FAX: E-mail: bernard.faydide@cea.fr
6328Cdrom A Study on Experiment and Numerical Analysis for Disclosing Shell Wall Thinning of a Feedwater Heater 6   4  
6099Cdrom Advanced Design Concept of Direct Vessel Injection 6.04   6.05  
6150Cdrom Water Jet Impingement Flow Characteristics in Direct Vessel Injection System 6   6  
6103Cdrom An Experimental Investigation for the Moisture Separation System of a Steam Generator 6    

6.06 Separate Effects Thermal Hydraulic Experiments & Analysis-II
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Pradip Saha, GE Energy - Nuclear; 3901 Castle Hayne Road, M/C L60 ; Wilmington, NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail: pradip.saha@ge.com
6075Cdrom Testing of a Compact Heat Exchanger for Use as the Cooler in a Supercritical CO2 Brayton Cycle 6    
6186Cdrom Study on Acoustic Resonance and It's Damping of BWR Steam Dome 6    
6358Cdrom Acoustic Analysis for a Steam Dome and Pipings of a 1,100 MWe-Class Boiling Water Reactor 6   5  
6130Cdrom Flow Characteristics Analysis of Widows' Creek Type Control Valve for Steam Turbine Control 6   6  

6.07 Integral Systems Thermal Hydraulic Experiments
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
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
6440Cdrom PKL Experiments on Loss of Residual Heat Removal under Shutdown Conditions in PWRs 6.   5.  
6351Cdrom Development of Conservative Method for Feedwater Pipe Break Analysis of an Integral Reactor 9    
6162Cdrom Testing of the Multi-Application Small Light Water Reactor (MASLWR) Passive Safety Systems 6   1  
6207Cdrom Large Scale Gas Mixing and Stratification Triggered by a Buoyant Plume with and without Occurrence of Condensation 6    

6.08 Systems Analysis & Assessment
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Bernard Faydide, CEA; , ; , France; Ph: FAX: 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
6387Cdrom Confirmatory Analysis of the AP1000 Passive Residual Heat Removal Heat Exchanger with 3-D Computational Fluid Dynamic Analysis 10   6  
6247Cdrom Recent Improvements to the RELAP5-3D Code 6    
6281Cdrom Investigation of Heat Transfer Mechanisms under Shutdown Plant Conditions with TRACE Code 6   5  
6327Cdrom Performance Analyses of ECCS and Containment Systems for the 4500MW ESBWR 6   5  
6066Cdrom Two-Phase Flow Studies in Nuclear Power Plant Primary Circuits Using the Three-Dimensional Thermal-Hydraulic Code BAGIRA 6    

6.10 Thermal Hydraulics Measurement and Modeling Fundamentals
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
Samim Anghaie, University of Florida; 202 NSC, University of Florida ; Gainesville , Florida 32611-8300 USA; Ph: 352-392-8653 FAX: 352-392-8656 E-mail: anghaie@ufl.edu
6004Cdrom Measurement and Simulation of a Two- Component Two-Phase Flow 6    
6121Cdrom Heat Transfer of the Wet Thermal Insulator with Multi-layer 6    
6143Cdrom The Thermal Hydraulic Test of the MEGAPIE Cooling System and System Code Validation 6   4  

Up

7.00: Core and Fuel Cycle Concepts and Experiments
Temitope Taiwo, ANL; , ; , USA; Ph: FAX: E-mail: Taiwo@ANL.gov
Chan Oh Park, KEPCO Nuclear Fuel Co. (KNFC); , ; , Korea; Ph: FAX: E-mail: copark@knfc.co.kr
Chang Lak Kim, KHNP-NETEC; P.O. Box 149, Yuseong ; Daejeon , 305-600 Korea; Ph: 82-42-870-0360 FAX: 82-42-870-0354 E-mail: clkim@khnp.co.kr
Dominique Greneche, COGEMA; 2, rue Paul Dautier, B.P. 4 ; 78141 Velizy Cedex , France; Ph: 33 1 39 26 37 54 FAX: 33 1 39 26 27 75 E-mail: dgreneche@cogema.fr
Toshikazu Takeda, Osaka University; , ; , Japan; Ph: FAX: E-mail: takeda@nucl.eng.osaka-u.ac.jp
Akio YAMAMOTO, Nagoya University; Dept. of Materials, Physics and Energy Engineering, Furo-cho, Chikusa-ku ; Nagoya, 464-8603 Japan; Ph: 81-52-789-5121 FAX: 81-52-789-3608 E-mail: a-yamamoto@nucl.nagoya-u.ac.jp

7.01 Innovations in Core Designs
THURSDAY, JUNE 8, 2006 • 1:00 P.M. - 3:00 P.M.
Toshikazu Takeda, Osaka University; , ; , Japan; Ph: FAX: E-mail: takeda@nucl.eng.osaka-u.ac.jp
6317Cdrom Development of Erbia-bearing Super High Burnup Fuel 7    
6153Cdrom EDF Nuclear Power Plants Operating Experience with MOX Fuel 7    
6206Cdrom Long Life Single Load Reactor Fuel 7    
6234Cdrom Transmutation Characteristics in a Pb-Bi Cooled Fast Reactor, PEACER-300 7   3  
6101Cdrom Fuel-cycle of CANDLE Burnup with Depleted Uranium 7    

7.02 Strategies for Advanced Fuel Cycles
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Won Sik Yang, ANL; , ; , USA; Ph: FAX: E-mail: wyang@anl.gov
6383Cdrom Impact of Advanced Fuel Cycle Options on Waste Management Policies 7   3  
6215Cdrom ADS Model in TIRELIRE-STRATEGIE Fuel Cycle Simulation Code: Application to Minor Actinides Transmutation Studies 7    
6272Cdrom A Strategy for Advanced Fuel Cycle Deployment 7    
6116Cdrom Smooth Transition from Light Water Reactors to Fast Breeder Reactors by Flexible Fuel Cycle Initiative (FFCI) 7   10  
6306Cdrom A Specific Long Term Plan for Management of U.S. Nuclear Spent Fuel    

7.03 Advanced Fuel Cycle Reprocessing Technology Issues
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
Dominique Greneche, COGEMA; 2, rue Paul Dautier, B.P. 4 ; 78141 Velizy Cedex , France; Ph: 33 1 39 26 37 54 FAX: 33 1 39 26 27 75 E-mail: dgreneche@cogema.fr
6323Cdrom Application of a Plasma Mass Separator to Advanced LWR Spent Fuel Reprocessing 7    
6233Cdrom Development in Waste Volume Reduction Technologies for Highly Contaminated Organic Radioactive Compounds    
6135Cdrom R&D of On-line Reprocessing Technology for Molten-Salt Reactor Systems 3.04   7.04  
6056Cdrom Cost Savings of Nuclear Power with Total Fuel Reprocessing 10   3  
6090Cdrom Heat Transfer Design for Ceramic Waste Forms From Pyroprocessing 9   10  

7.04 Advanced Fuel Cycles, Recycling, and Actinide Transmutation
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
Temitope Taiwo, ANL; , ; , USA; Ph: FAX: E-mail: Taiwo@ANL.gov
6400Cdrom Coupled Hybrid Monte Carlo - Deterministic Analysis of VHTR Configurations with Advanced Actinide Fuels 7   2  
6151Cdrom Minor Actinides Recycling in PWRs 7   1  
6197Cdrom Actinide Transmutation Using Pressurized Water Reactors 7   1  
6133Cdrom Neptunium as a Tool for Reducing Proliferation Risks with Plutonium: A Technical Analysis of its Efficiency and its Drawbacks 7   9  

7.05 Characterization of Fuel Cycle Design Options
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 3:00 P.M.
M. Todosow, BNL; 12 South Upton Rd., Building 475B PO Box 5000; Upton, NY 11973-5000 USA; Ph: 631-344-2445 FAX: 631-344-7650 E-mail: todosowm@bnl.gov
6296Cdrom Non-Invasive Characterisation of Burnup for PWR Spent Fuel Rods with Burnups > 80 GWd/t 7    
6113Cdrom Toxicity of Radioactive Wastes Generated from PEACER in Korea 9   7  
6410Cdrom Micro X-ray Radiography for the Coating Thickness Measurement in the Simulated TRISO-coated Fuel Particle 7    
6271Cdrom HELIOS: Irradiation of U-free Fuels and Targets for Americium Transmutation 7    
6417Cdrom Feasibility Study of MOX Fuel Online Burnup Analysis 7   11  

Up

8.00: Materials and Structural Issues
Todd Allen, University of Wisconsin; 1500 Engineering Drive, ; Madison, WI USA; Ph: 608-265-4083 FAX: 608-263-7451 E-mail: allen@engr.wisc.edu
Travis W. Knight, University of South Carolina; Dept of Mechanical Engineering, 300 Main Street ; Columbia , SC 29208 USA; Ph: 803-777-1465 FAX: 803-777-0106 E-mail: knighttw@engr.sc.edu
Woo-Seog Ryu, KAERI; , ; , Korea; Ph: FAX: E-mail: wsryu@kaeri.re.kr
Sung-Yull Hong, KEPRI; , ; , Korea; Ph: FAX: E-mail: syhong@kepri.re.kr
Françoise Touboul, CEA; CEA Saclay, DEN/DM2S Batiment 454; Gif sur Yvette, 91191 France; Ph: 33 1 69 08 68 18 FAX: 33 1 69 08 66 42 E-mail: francoise.touboul@cea.fr
Kunihiro ITOH, Nuclear Development Corp; 622-12, Funaishikawa ; Tokaimura, Ibaraki 319-1111 Japan; Ph: 81-29-282-9117 FAX: 81-29-283-0405 E-mail: itoh@ndc.hq.mhi.co.jp

8.01 Structural and Materials Modeling and Analysis-I
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Ram Srinivasan, BNG Fuel Solutions; 2105 S. Bascom Av, #160, ; Campbell , CA 95008 USA; Ph: (408)558-3510 FAX: (408)558-3518 E-mail: rsrinivasan@bngamerica.com
6290Cdrom Application of USNRC NUREG/CR-6661 and Draft DG-1108 to Evolutionary and Advanced Reactor Designs 8    
6385Cdrom Structural Integrity of ESBWR Primary Containment for 60-Years of Thermal Duty Cycle Operations 8    
6384Cdrom Evaluation of Liner Backpressure Due to Concrete Pore Pressure at Elevated Temperatures 8    
6349Cdrom Assessment of Analytical Prediction of JNES Seismic Wall Pressure Data for ABWR Model Structures 8    

8.01 Structural and Materials Modeling and Analysis-II
TUESDAY, JUNE 6, 2006 • 2:30 P.M. - 4:00 P.M.
Ram Srinivasan, BNG Fuel Solutions; 2105 S. Bascom Av, #160, ; Campbell , CA 95008 USA; Ph: (408)558-3510 FAX: (408)558-3518 E-mail: rsrinivasan@bngamerica.com
6080Cdrom Buckling of Thin Cylindrical Shell Subject to Uniform External Pressure 1   8  
6046Cdrom Effect of Pipe Size on the Leak-Before-Break Recommended Safety Margins in a Typical Pressurized Water Reactor 8    
6283Cdrom Embrittlement Problems of Metal Structures of Nuclear Power Plants 8    
6458Cdrom Low Cycle Fatigue Behaviour of Irradiated Stainless Steel As Shielding Material    

8.02 Testing and Analysis of Structures and Materials
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 3:00 P.M.
Françoise Touboul, CEA; CEA Saclay, DEN/DM2S Batiment 454; Gif sur Yvette, 91191 France; Ph: 33 1 69 08 68 18 FAX: 33 1 69 08 66 42 E-mail: francoise.touboul@cea.fr
6138Cdrom Influence of Hydrogen Content on Axial Fracture Toughness Parameters of Zr-2.5Nb Pressure Tube Alloy in the Temperature Range of 306-573 K 8   5  
6029Cdrom On the Creep Behavior of Niobium-modified Zirconium Alloys 8    
6350Cdrom Effects of Hydrogen on the Fatigue Crack Growth Rate of Low Alloy Steels 8    
6428Cdrom Microstructural Examination of the Effect of Surface Machining on Stress Corrosion Cracking in Core Shroud Made of 316L 8   8  
6060Cdrom Corrosion Processes of the CANDU Steam Generator Materials in the Presence of Silicon Compounds 8    

8.03 Fuel Design and Irradiation Issues for Next Generation Plants
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Travis W. Knight, University of South Carolina; Dept of Mechanical Engineering, 300 Main Street ; Columbia , SC 29208 USA; Ph: 803-777-1465 FAX: 803-777-0106 E-mail: knighttw@engr.sc.edu
6185Cdrom Comparison of the 3 MeV C+ Irradiation Effects between the Nuclear Graphite Made of Pitch and Petroleum Cokes 8    
6422Cdrom Advanced GFR Utilizing NITE-SiC/SiC Shield Fuel Pin 8   2  
6068Cdrom Evaluation of Specialized Thermocouples for High-Temperature In-Pile Testing 7   6  
6431Cdrom A New Facility for the Irradiation of Materials at Very High Temperatures 2    

8.04 Materials Issues for Next Generation Plants-I
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Jim Cole, INL; PO Box 1625, MS 6188 ; Idaho Falls, ID 83403 USA; Ph: 208-533-7165 FAX: E-mail: jim.cole@inl.gov
6170Cdrom Corrosion Rate Evaluations of Structural Materials for Iodine-Sulfur Thermochemical Water Splitting Cycle 2   9  
6163Cdrom Modeling on Oxygen Transfer in the Nature Convection Lead-bismuth Eutectic Flow 6   8  
6235Cdrom Corrosion and Stress Corrosion Cracking of High Cr Ferritic-Martensitic Steels in Supercritical Water 8    
6137Cdrom SCC Properties of Candidate Alloys for SCWR Core Components 8   1  
6468Cdrom Critical Issues on Selection of Candidate Materials for Out-of-Core Structural Applications in Generation IV Nuclear Reactors 8.04    

8.05 Materials Issues for Next Generation Plants-II
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
Todd Allen, University of Wisconsin; 1500 Engineering Drive, ; Madison, WI USA; Ph: 608-265-4083 FAX: 608-263-7451 E-mail: allen@engr.wisc.edu
6368Cdrom Development of Advanced Control Rod of Hafnium Hydride for Fast Reactors 8    
6171Cdrom Master Curve and Conventional Fracture Toughness of Modified 9Cr-1Mo Steel 8    
6236Cdrom Response of 9Cr Steel and 20Cr Fe-base ODS Alloy to High-energy Ne Ion Irradiation at Elevated Temperatures 8    
6456Cdrom Fuel Clad Materials R&D for High Burn-up Operation of Advanced Nuclear Energy Systems 8    

Up

9.00: Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications
Layla Sandell, EPRI; 3412 Hillview Avenue , ; Palo Alto , CA 94304 USA; Ph: 650-855-2756 FAX: 650-855-2002 E-mail: LSANDELL@epri.com
Ken Schultz, General Atomics; P.O. Box 85608, ; San Diego, CA 92186-5608 USA; Ph: 858-455-4304 FAX: 858-455-2838 E-mail: ken.schultz@gat.com
Won Seok Park, KAERI ; , ; , Korea; Ph: 82-42-868-8375 FAX: E-mail: wonpark@kaeri.re.kr
Sung Kyun Zee, KAERI; 150 Dukjin-dong, Yuseong, ; Daejon, 305-353 Korea; Ph: 82-42-868-2747 FAX: 82-42-868-8990 E-mail: zee@kaeri.re.kr
Bernard Bonin, CEA; , ; , France; Ph: FAX: E-mail: bernard.bonin@cea.fr
Shoji KATANISHI, Japan Atomic Energy Agency (JAEA); , ; Oarai-machi, Ibaraki-ken 311-1393 Japan; Ph: 81-29-266-7718 FAX: 81-29-266-7608 E-mail: katanishi.shoji@jaea.go.jp
Masaki UOTANI, CRIEPI; 2-11-1, Iwadokita ; Komae-shi, Tokyo 201-8511 Japan; Ph: 81-3-3480-2111 Ext. 1140 FAX: 81-3-3480-7950 E-mail: uotani@criepi.denken.or.jp

9.01 Nuclear Hydrogen Production: Thermochemical
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
Ken Schultz, General Atomics; P.O. Box 85608, ; San Diego, CA 92186-5608 USA; Ph: 858-455-4304 FAX: 858-455-2838 E-mail: ken.schultz@gat.com
Ed Lahoda, Westinghouse; 1344 Beulah Rd, ; Pittsburgh, PA 15235-5083 USA; Ph: 412-256-2238 FAX: 412-256-2444 E-mail: lahodaej@westinghouse.com
6024Cdrom Hydrogen Production by Using Heat from High-temperature Gas-cooled Reactor HTTR; HTTR-IS Plan 9   2  
6166Cdrom Development of Sulfuric Acid Decomposer for Thermo-Chemical IS Process 9    
6107Cdrom Nuclear Hydrogen Production Based on the Hybrid Suflur Thermochemical Process 9    
6102Cdrom An Experiment on Methane-Methanol-Iodomethane Cycle to Produce Nuclear Hydrogen 9    

9.02 Nuclear Hydrogen Production: Electrolysis Processes
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Layla Sandell, EPRI; 3412 Hillview Avenue , ; Palo Alto , CA 94304 USA; Ph: 650-855-2756 FAX: 650-855-2002 E-mail: LSANDELL@epri.com
John M (Jack) Tuohy, Hitachi America; Power Systems Division, 50 Prospect Avenue ; Tarrytown, , NY 10591-4625 USA; Ph: 914-524-6671, 201-410-5755 Cell FAX: E-mail: tuohyj@alum.mit.edu,john.tuohy@hal.hitachi.com
6425Cdrom Revised Capital and Operating HyS Hydrogen Production Costs 2.05    
6282Cdrom Hydrogen Production System with High Temperature Electrolysis for Nuclear Power Plant 9    
6062Cdrom Separation Requirements for a Hydrogen Production Plant and High-Temperature Nuclear Reactor 5   2  
6222Cdrom Simulation Modeling of a Tubular-type Solid Oxide Electrolysis Cell for Hydrogen Production on Nuclear Power Plant 9    
6251Cdrom Development of Flow Net Solver for HyPEP: A Hydrogen Production Plant Efficiency Calculation Program    

9.03 Economics and Environmental Aspects of Nuclear Energy-I
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 2:30 P.M.
Ed Lahoda, Westinghouse; 1344 Beulah Rd, ; Pittsburgh, PA 15235-5083 USA; Ph: 412-256-2238 FAX: 412-256-2444 E-mail: lahodaej@westinghouse.com
Layla Sandell, EPRI; 3412 Hillview Avenue , ; Palo Alto , CA 94304 USA; Ph: 650-855-2756 FAX: 650-855-2002 E-mail: LSANDELL@epri.com
6007Cdrom Production of Liquid Synthetic Fuels from Carbon, Water and Nuclear Power on Ships and at Shore Bases for Military and Potential Commercial Applications 9    
6336Cdrom Market Penetration Simulation of Hydrogen Powered Vehicles in Korea 9   10  
6104Cdrom High-Temperature Reactors for In Situ Recovery of Oil from Oil Shale 9    
6442Cdrom Nuclear Energy for Oil Extraction in Canadian Tar Sands: Integration of Nuclear Power with In-Situ Oil Extraction 9.04    

9.04 Economics and Environmental Aspects of Nuclear Energy-II
THURSDAY, JUNE 8, 2006 • 1:00 P.M. - 3:00 P.M.
John M (Jack) Tuohy, Hitachi America; Power Systems Division, 50 Prospect Avenue ; Tarrytown, , NY 10591-4625 USA; Ph: 914-524-6671, 201-410-5755 Cell FAX: E-mail: tuohyj@alum.mit.edu,john.tuohy@hal.hitachi.com
Ken Schultz, General Atomics; P.O. Box 85608, ; San Diego, CA 92186-5608 USA; Ph: 858-455-4304 FAX: 858-455-2838 E-mail: ken.schultz@gat.com
6302Cdrom Economics of Nuclear Process Heat Applications 9   2  
6154Cdrom The Modular Helium Reactor for Future Energy Needs 9   2  
6343Cdrom Economic Considerations of Nuclear Desalination in Korea 9   10  
6258Cdrom Future Energy System in Environment, Economy, and Energy Problems: Nuclear System as a Solution to the E3 Trilemma 9    
6308Cdrom Future Energy System in Environment, Economy, and Energy Problems: (2) Various Nuclear Energy System Evaluations 9    
6291Cdrom Innovative Nuclear Reactors Implementation in the Armenian Energy Sector    
6476Cdrom Public Acceptance of Nuclear Energy in México 9.04    

Up

10.00: Near Term Issues
Terry L. Schulz , Westinghouse Electric Co; 4350 N. Pike, ; Monroeville, PA 15146 USA; Ph: 412-374-5120 FAX: 412-374-5005 E-mail: schulztl@westinghouse.com
Seung-J. Oh, KHNP; , ; , Korea; Ph: 82-42-865-5703 FAX: E-mail: se_oh@khnp.co.kr
Hie-sun Lee, KHNP; , ; , Korea; Ph: FAX: E-mail: leehso@khnp.co.kr
Alain Calamand, Framatome ANP; Tour AREVA, 1, Place de la Coupole ; PARIS-LA-DEFENSE Cedex, 92084 France; Ph: 33 1 47 96 38 08 FAX: 33 1 47 96 00 46 E-mail: alain.calamand@framatome-anp.com
Shoji Goto, TEPCO; Tokyo Electric Power Company , 4-1 Egasaki-cho Tsurumi-ku; Yokohama, 230-8510 Japan; Ph: 81-45-613-6704 FAX: 81-45-613-7899 E-mail: goto.shoji@tepco.co.jp
Kazuaki Matsui, Institute of Applied Energy (IAE); 14-2 Nishishinbasho, 1-chome, Minato-ku ; Tokyo , 105-0003 Japan; Ph: 81-3-3508-8894 FAX: 81-3-3501-1735 E-mail: mac@iae.or.jp

10.01 Near Term Issues
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
Terry L. Schulz , Westinghouse Electric Co; 4350 N. Pike, ; Monroeville, PA 15146 USA; Ph: 412-374-5120 FAX: 412-374-5005 E-mail: schulztl@westinghouse.com
6405Cdrom Licensing the Next Generation of Nuclear Power Plants 10    
6366Pres. Near-Term Deployment of New Nuclear Generation 10    
6263Cdrom The NuStart AP1000 Compact Control Room Implementation 10    
6245Cdrom The Need for an International Quality Standard 4   10  
6058Cdrom Nuclear Reactors in Deregulated Markets: Integration between Providers and Customers? 10    

Up

11.00: Reactor Physics and Analysis
Bojan Petrovic, Westinghouse; Westinghouse Science and Technology , 1344 Beulah Rd ; Pittsburgh , PA 15235 USA; Ph: 412-256-1295 FAX: 412-256-2444 E-mail: PetrovB@westinghouse.com
Han Gyu Joo, Seoul National Univ; , ; , Korea; Ph: FAX: E-mail: joohan@snu.ac.kr
Jae-Man Noh, KAERI; Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu ; Daejeon, 305-353 Korea; Ph: 82-42-868-2654 FAX: 82-42-864-1089 E-mail: jmnoh@kaeri.re.kr
Richard Sanchez, CEA; , ; , France; Ph: FAX: E-mail: richard.sanchez@cea.fr
Tadashi YOSHIDA, Musashi Institute of Technology; 1-25-1 Tamazutsumi, Setagaya-ku ; Tokyo, 159-8557 Japan; Ph: 81-3-5707-1168 FAX: 81-3-5707-1168 E-mail: yos@ph.ns.musashi-tech.ac.jp

11.01 Reactor Physics Methods/Codes-I
WEDNESDAY, JUNE 7, 2006 • 1:00 P.M. - 2:30 P.M.
Han Gyu Joo, Seoul National Univ; , ; , Korea; Ph: FAX: E-mail: joohan@snu.ac.kr
6089Cdrom Development of a Computer Code System for the Analysis of VHTR Cores 2   11  
6286Cdrom Optimal Refueling Pattern Search for a CANDU Reactor Using a Genetic Algorithm 7   11  
6360Cdrom ERANOS 2.1: The International Code System for GENIV Fast Reactor Analysis 11   11  
6412Cdrom Enhanced Monte Carlo Linked Depletion Capabilities in MCNPX 11    

11.01 Reactor Physics Methods/Codes-II
WEDNESDAY, JUNE 7, 2006 • 2:30 P.M. - 4:00 P.M.
Richard Sanchez, CEA; , ; , France; Ph: FAX: E-mail: richard.sanchez@cea.fr
6337Cdrom Assembly Based Modular Ray Tracing and CMFD Acceleration for BWR Cores with Different Fuel Lattices 11    
6049Cdrom Sensitivity Analysis Based on Transport Theory for Innovative Reactor 11   7  
6021Cdrom AttilaR Modeling with Comparisons to Data, MCNP and MCNPX for the Advanced Test Reactor (ATR)    
6018Cdrom Verification of Optimal Control Strategy Search Using a Simplest 3-D PWR Xenon Oscillation Simulator 4   11  
6441Cdrom A New Hybrid Optimization Method for Loading Pattern Search    

11.02 New Core/Reactor Concepts
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Bojan Petrovic, Westinghouse; Westinghouse Science and Technology , 1344 Beulah Rd ; Pittsburgh , PA 15235 USA; Ph: 412-256-1295 FAX: 412-256-2444 E-mail: PetrovB@westinghouse.com
6355Cdrom Neutronic and Physical Characteristics of Reactor SVBR 75/100 with Different Types of Fuel 7    
6354Cdrom Local-Spectrum-Modified Fast Reactor Cores with Hydrides 7   11  
6157Cdrom Safe Fast Reactor Based on Nuclear Burning Wave Regime 3   11  
6020Cdrom Small PWR Using Coated Particle Fuel with Ceramics Cladding 1   7  
6156Cdrom Wire Wrapped Fuel Pin Hexagonal Arrays for PWR Service 1   7  

11.03 Reactor Physics Analyses and Applications
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 2:30 P.M.
Jae-Man Noh, KAERI; Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu ; Daejeon, 305-353 Korea; Ph: 82-42-868-2654 FAX: 82-42-864-1089 E-mail: jmnoh@kaeri.re.kr
6459Cdrom Boiling Water Reactor Fuel Cycle Optimization for Prevention of Channel-Blade Interference 11    
6167Cdrom Comparison of SFRs and LFRs as Waste Burners 3   11  
6095Cdrom Calculation of the Local Neutronic Parameters for CANDU Fuel Bundles Using Transport Methods 11. Reactor Physics and Analysis    

11.04 Validation of Reactor Physics Methods
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
Jacopo Saccheri, BNL; , ; , USA; Ph: FAX: E-mail: saccheri@bnl.gov
6315Cdrom SCALE 5.0 Reactor Physics Assessment using the Module TRITON against Mixed Oxide (MOX) OECD/NEA Benchmarks 11    
6180Cdrom Neutron Fluence Vessel Assessment in the 1300MWe NPP French Fleet: The FLUOLE Program in EOLE 1   11  
6077Cdrom Analysis of Reactor Physics Experiment for the Irradiated LWR MOX Fuels 11   7  

Up

12.00: Space Power and Propulsion
Michael Houts , NASA MSFC; Nuclear Systems Office / NP50, ; MSFC , AL 35812 USA; Ph: 256-544-8136 FAX: 256-544-6696 E-mail: michael.g.houts@nasa.gov
Melissa K. Van Dyke , NASA/MSFC; TD40, ; Huntsville , AL 35812 USA; Ph: 256-544-5720 FAX: 256-544-5926 E-mail: Melissa.VanDyke@nasa.gov
Myung-Hyun Kim, KHU; , ; , Korea; Ph: 82-31-201-2562 FAX: E-mail: mhkim@khu.ac.kr
Xavier Raepsaet, CEA; CEA/Saclay Bat. 470, DEN/DM2S/SERMA/LCA ; GIF-sur-YVETTE CEDEX, 91191 France; Ph: 33 1 69 08 46 64 FAX: 33 1 69 08 99 35 E-mail: xavier.raepsaet@cea.fr

12.01 Space Nuclear Power and Propulsion Systems
THURSDAY, JUNE 8, 2006 • 10:00 A.M. - 12:00 P.M.
David Poston, Los Alamos National Laboratory; Nuclear Systems Design and Analysis Group, MS-K551 ; Los Alamos, NM 87545 USA; Ph: 505-667-4336 FAX: 505-665-3167 E-mail: poston@lanl.gov
6413Cdrom Comparison of Reactor Technologies and Designs for Lunar/Martian Surface Reactor Applications 12    
6297Cdrom A Practical Approach to Starting Fission Surface Power Development 12   3  
6363Cdrom Evaluation of an Integrated Gas-Cooled Reactor Simulator and Brayton Turbine-Generator 12   3  
6253Cdrom Passive Reactor Cooling Using Capillary Porous Wick 12    
6065Cdrom Self-Driven Decay Heat Removal in a GCR Closed Brayton Cycle Power System 12   2  

12.02 Lunar/Mars Surface Power
TUESDAY, JUNE 6, 2006 • 1:00 P.M. - 3:00 P.M.
Michael Houts , NASA MSFC; Nuclear Systems Office / NP50, ; MSFC , AL 35812 USA; Ph: 256-544-8136 FAX: 256-544-6696 E-mail: michael.g.houts@nasa.gov
6414Cdrom Reduced-Enrichment, Fast-Spectrum Lunar/Mars Surface Reactors 12    
6392Cdrom Thermal-Structural Design of Water Shield for Surface Reactor Missions 12    
6391Pres. Surface Power Fission System Fuels: Safeguards Cost Implications of Fuel Inventory 12    
6389Pres. Demonstrating the Viability and Affordability of Nuclear Surface Power Systems 12   3  
6388Cdrom Surface Power Fission System Fuels: Technology Readiness and Qualification Issues 12   8  
6370Cdrom Options for Affordable Fission Surface Power Systems 12   3  

12.03 Test and Design Methods for Space Reactor Systems
WEDNESDAY, JUNE 7, 2006 • 10:00 A.M. - 12:00 P.M.
Tom Marcille, LANL; , ; , USA; Ph: (505)667-2762 FAX: E-mail: tmarcille@lanl.gov
6381Cdrom Autonomous Control and Diagnostics of Space Reactor Systems 12    
6479Cdrom The Value of A Nuclear Ground Test 12.03    
6050Cdrom Space Power System Modeling with EBAL 12   11  

12.04 Advanced Concepts in Space Nuclear Power
TUESDAY, JUNE 6, 2006 • 10:15 A.M. - 12:15 P.M.
Michael LaPointe, NASA MSFC; Nuclear Systems Office / VP31, George C. Marshall Space Flight Center Huntsville; Huntsville, AL 35812 USA; Ph: (256)544-2648 FAX: 256-544-6969 E-mail: michael.r.lapointe@nasa.gov
Pavlos Mikellides, Arizona State Univ; College of Engineering and Applied Sciences, Department of Mechanical and Aerospace Engineering P.O. Box 876106; Tempe, AZ 85287-6215 USA; Ph: (480) 727-6215 FAX: E-mail: Pavlos.Mikellides@asu.edu
6465Cdrom Energy Deposition via Magnetoplasmadynamic Acceleration 12.04    
6012Cdrom MOA: Magnetic Field Oscillating Amplified Thruster and its Application for Nuclear Electric and Thermal Propulsion 12    
6408Cdrom A Comparison of the Performance Capabilities of Radioisotope Energy Conversion Systems, Betavoltaic Cells, and other Nuclear Batteries 12    
6205Pres. Space Shuttle Nuclear Antenna for Deep Space Remote Power Transfer 12    

12.05 Materials for Space Reactor Concepts
MONDAY, JUNE 5, 2006 • 2:30 P.M. - 4:00 P.M.
Robert Hickman, NASA; , ; , USA; Ph: (256)544-8578 FAX: E-mail: robert.r.hickman@nasa.gov
Cheryl Bowman, NASA Glenn Research Center; Materials & Structures Division, MS 301-2 21000 Brookpark Rd. ; Cleveland, OH 44135 USA; Ph: (216) 433-8462 FAX: (216) 433-6133 E-mail: Cheryl.L.Bowman@nasa.gov
6379Cdrom Life Testing of Refractory Metal / Sodium Heat Pipes 12   3  
6377Pres. Preliminary Analysis of a Water Shield for a Surface Power Reactor 12    
6331Cdrom Design, Fabrication and Integration of a NaK-Cooled Circuit 12   6  
6030Cdrom High Temperature Mechanical Properties of Molybdenum Solid Solution Alloys 12   8  

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The last update is: Fri May 12 11:52:26 2006