2008 International Congress on Advances in Nuclear Power Plants (ICAPP '08)

Embedded International Topical Meeting at the 2008 ANS Annual Meeting

June 8-12, 2008    Anaheim, California, USA   Disneyland Hotel

Home Organizers Call For Papers Papers/Program Highlights Anaheim/Hotel 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

11.00: Reactor Physics and Analysis

12.00: Innovative and Space Reactor Systems

13.00: Plant Licensing Issues
14.00: Plenary Sessions

 

Up

0.00: Unassigned Abstracts/Papers
8444Abs.r davai 1   2  

Up

1.00: Water-Cooled Reactor Programs and Issues
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
MD Alamgir, GE-Hitachi Nuclear Energy; 3901 Castle Hayne Road, P.O. Box 780, MC A51 ; Wilmington , NC 28402 USA; Ph: 910 675 5562 FAX: 910 362 5562 E-mail:md.alamgir@ge.com
Philippe Lauret, AREVA NP; , ; , France; Ph: FAX: E-mail:philippe.lauret@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
Shigemitsu Otsuka, MHI; 16-5, KONAN-2-CHOME MINATO-KU; TOKYO, 108-8215 Japan; Ph: 81-3-6716-4950 FAX: 81-3-6716-5882 E-mail:shigemitsu_otsuka@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

1.01 Innovative/Evolutionary, Advanced PWRs
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
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
Shigemitsu Otsuka, MHI; 16-5, KONAN-2-CHOME MINATO-KU; TOKYO, 108-8215 Japan; Ph: 81-3-6716-4950 FAX: 81-3-6716-5882 E-mail: shigemitsu_otsuka@mhi.co.jp
8338Cdrom IRIS: A Comprehensive Approach to Nuclear Power in Smaller-Sized and Developing Countries 10   1  
8110Cdrom Justification and Manufacturing Quality Assurance for the Use of Hot Isostatically Pressed, Reactor Coolant System Components in PWR Plant 1   8 or 13  
8249Cdrom EPR: High Load Variation Performances with the Tmode Core Control 1   4  
8237Cdrom An Integrated PWR for Marine Propulsion 1   12  
8031Cdrom European Passive Plant (AP1000 -Europe) Design Status 1    

1.02 Innovative/Evolutionary, Advanced BWRs
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
MD Alamgir, GE-Hitachi Nuclear Energy; 3901 Castle Hayne Road, P.O. Box 780, MC A51 ; Wilmington , NC 28402 USA; Ph: 910 675 5562 FAX: 910 362 5562 E-mail: md.alamgir@ge.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
8411Cdrom The Safety Concept of the SWR 1000 with Active and Passive Safety Systems 1    
8389Cdrom SWR 1000: Efficient Design for Operational Excellence 1    
8345Cdrom ESBWR Power Maneuvering via Feedwater Temperature Control 1   4  
8341Cdrom Role of Human Factors in System Safety 1   2  
8228Cdrom Coupled Regional Stability Analysis of Natural Circulation BWRs 1   6  
8054Cdrom SWR 1000 Integral and Full Scale Tests of the Passive Safety Systems 6   1  

1.03 Advanced Plant Delivery - Meeting Industry Challenges-I
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
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
Philippe Lauret, AREVA NP; , ; , France; Ph: FAX: E-mail: philippe.lauret@areva.com
8410Cdrom Optimization Planning for the Construction of the U.S. EPR 1   4  
8317Cdrom Experimental Investigation of Non-condensable Gases Effect on Operation of VVER Steam Generator in Condensation Mode 1   6  
8091Cdrom European Research on Issues Concerning Hydrogen Behaviour in Containment within the SARNET Network of Excellence 1    
8036Cdrom Economic Advantage of the Korea Nuclear Plants by Shortening the Construction Schedule 1    

1.03 Advanced Plant Delivery - Meeting Industry Challenges-II
THURSDAY, JUNE 12 1:00 P.M. - 3:00 P.M.
Philippe Lauret, AREVA NP; , ; , France; Ph: FAX: E-mail: philippe.lauret@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
8216Cdrom Study on High Conversion Type Core of Flexible Fuel Cycle (FLWR) for Minor Actinide (MA) Recycling 1.02    
8417Cdrom A Review of Dopants Used to Increase UO2 Burnup Capabilities by Grain Size Modification 8    
8004Cdrom A Comparative Evaluation of Pressurizer Surge Line Thermal Loads 4   8  

Up

2.00: High Temperature Gas Cooled Reactors
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
Kevan D. Weaver, Intellectual Ventures; , ; , USA; Ph: FAX: E-mail:kweaver@intven.com
Patrick Dumaz, CEA; , ; , France; Ph: FAX: E-mail:patrick.dumaz@cea.fr
Michael A. Ftterer, 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
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
Zuoyi Zhang, INET; , ; , China; Ph: FAX: E-mail:zyzhang@tsinghua.edu.cn

2.01 HTR Concepts and Design Innovations
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Pavel Tsvetkov, Texas A&M Univ; 129 Zachry, MS 3133, ; College Station, TX 77843 USA; Ph: 979-845-7078 FAX: 979-845-6443 E-mail: tsvetkov@tamu.edu
8433Cdrom Why HTR/VHTR? A European Point of View 2   9  
8211Cdrom Design, Analysis and Development for the Modular PB-AHTR 2   3  
8079Cdrom Using Helicoids to Eliminate Hot Streaking and Stratification in the Very High Temperature Reactor Lower Plenum 2   6  
8103Cdrom Risk Minimization for Near-Term Deployment of the Next Generation Nuclear Plant 2   10  
8104Cdrom Neutronic Performance of High Molecular Weight Coolants for a Prismatic VHTR 1   11  

2.02 GFR and Other Advanced Concepts
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Kevan D. Weaver, Intellectual Ventures; , ; , USA; Ph: FAX: E-mail: kweaver@intven.com
8175Cdrom Gas Cooled Fast Reactor 2400 MWth, End of the Preliminary Viability Phase 2   3  
8289Cdrom Studies of Unprotected Transients and Alternative Decay Heat Removal System for the Gas Cooled Fast Reactor (GFR) 2   3  
8184Cdrom Preliminary Safety Analysis of the 2400 MWth Gas-cooled Fast Reactor 2   5  
8253Cdrom Power Conversion System (PCS) Evaluation for the Next Generation Nuclear Plant (NGNP) 2   10  

2.03 HTR Fuel and High Temperature Materials
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Paul Demkowicz, INL; Idaho National Lab, 2525 N Fremont Ave MS 3860; Idaho Falls, ID 83415-3860 USA; Ph: 208-526-3846 FAX: 208-526-2930 E-mail: Paul.Demkowicz@inl.gov
8093Cdrom Means, Methods and Performances of the AREVAs HTR Compact Controls 2   8  
8097Cdrom Developments and Economical Aspects in the Fabrication of HTR Fuel Elements 2. 03   7  
8147Cdrom Development of a Fission Product Release Analysis Code COPA-FPREL 2.06    
8241Cdrom Review of Material Properties of Pyrolytic Carbon Coating Layers in Relation with QC Measurement in HTR Coated Particle Fuels 2    
8008Cdrom Alloy 617 for the High Temperature Diffusion-Bonded Compact Heat Exchangers 2   8  

2.04 Advanced Fuel Cycle Development
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Matt Richards, General Atomics; P.O. Box 85608, ; San Diego, CA 92186-5608 USA; Ph: (858) 455-2457 FAX: (858) 455-2599 E-mail: matt.richards@gat.com
8134Cdrom An Optimal Loading Principle of Burnable Poisons for an OTTO Refueling Scheme in Pebble Bed HTGR Cores 2    
8233Cdrom Out-of-Core Fuel Cycle Characteristics of VHTRs with No On-Site Refueling 2   7  
8021Cdrom Deployment of FBR/VHTR Systems for Japan's Future Energy Demands 2   3  

2.06 Modeling and Simulation of GCRs
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Patrick Dumaz, CEA; , ; , France; Ph: FAX: E-mail: patrick.dumaz@cea.fr
8023Cdrom Implications of Air Ingress Induced by Density-Difference Driven Stratified Flow 2.06    
8128Cdrom A Three-Dimensional Heat Transfer Analysis on the Prismatic Fuel Elements in the Very High Temperature Reactor 2.6   6.7  
8177Cdrom 3D Thermal Simulation of Decay Heat Removal in a HTR Half Geometry 2    
8180Cdrom TINTE Transient Results for the OECD PBMR 400 MW PBMR Benchmark 2   11  

2.07 Power Conversion Systems and Non-Electric Applications
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
Michael A. Ftterer, 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
8072Cdrom Alternative Working Fluids to Reduce the Size of Turbomachinery in VHTR Plants 2   2  
8277Cdrom Thermo-Economic Performance of HTGR Brayton Power Cycles 2    
8382Cdrom Thermo-Chemical Behavior of a Laboratory Scale SO3 Decomposer 2.07   6.09  

Up

3.00: LMFR & Longer Term Reactor Programs
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
Charles Forsberg, MIT; Room 24-207A, 77 Massachusetts Avenue ; Cambridge, MA 02139 USA; Ph: (617)324-4010 FAX: E-mail:cforsber@mit.edu
Pradip Saha, GE-Hitachi Nuclear Energy; 3901 Castle Hayne Road, M/C A51 ; Wilmington , NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail:pradip.saha@ge.com
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
Jean-Pol Serpanti, AREVA NP; 10 rue Juliette Recamier, ; LYON, F-69456 LYON CEDEX 06 France; Ph: 33 (0) 4 72 59 02 17 FAX: E-mail:jeanpol.serpantie@areva.com
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
Pavel Alekseev, ; , ; , Russia; Ph: FAX: E-mail:apn@dhtp.kiae.ru

3.01 Advanced Burner/Recycling Reactors (Invited Session)
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Mario D. Carelli, Westinghouse STC; Energy Systems Engineering, 1310 Beulah Road ; Pittsburgh , PA 15235 USA; Ph: 412-256-1042 FAX: 412-256-2444 E-mail: carellmd@westinghouse.com
Pradip Saha, GE-Hitachi Nuclear Energy; 3901 Castle Hayne Road, M/C A51 ; Wilmington , NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail: pradip.saha@ge.com
8401Cdrom Sodium Fast Reactors (SFRs) and Recyclers 3.01    
8378Cdrom Near-term Deployment of the PRISM Sodium-cooled Fast Reactor 3   7  
8397Cdrom Approach for FBR Commercialization in Japan 3.01    
8402Cdrom An Innovative Design Approach to a Cost Effective Commercial Liquid Metal Reactor 3.01    
8404Abs.a French Sodium Fast Reactor Program 3.01    

3.02 Reprocessing Technology (Invited Session)
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Pradip Saha, GE-Hitachi Nuclear Energy; 3901 Castle Hayne Road, M/C A51 ; Wilmington , NC 28401 USA; Ph: 910-675-5498 FAX: (910) 362-5498 E-mail: pradip.saha@ge.com
Eric Loewen, GE Hitachi Nuclear Energy; , ; , USA; Ph: FAX: E-mail: eric.loewen@ge.com
8415Abs.a Aqueous Processing Technologies for the Treatment of Spent Nuclear Fuel 3.02    
8413Abs.a The Electrochemical Fuel Cycle for Treatment of Fast Reactor Fuel 3.02   3.01  
8407Abs.a Pyroprocessing Technologies for the Treatment of LWR Spent Fuel 3.02    
8398Abs.a French-Japan Fuel Cycle and SFR Development Program in the Context of GNEP 3    

3.03 Sodium-cooled Fast Reactors (SFR)-I
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Eric Loewen, GE Hitachi Nuclear Energy; , ; , USA; Ph: FAX: E-mail: eric.loewen@ge.com
Jean-Pol Serpanti, AREVA NP; 10 rue Juliette Recamier, ; LYON, F-69456 LYON CEDEX 06 France; Ph: 33 (0) 4 72 59 02 17 FAX: E-mail: jeanpol.serpantie@areva.com
8158Cdrom Design Approaches from Breakeven Core to TRU Burner Core Based on KALIMER-600 Reactor 3   02  
8074Cdrom Conceptual Core Designs for a 1200MWe Sodium Cooled Fast Reactor 3   11  
8071Cdrom Improving SFR Economics through Innovations from Thermal Design and Analysis Aspects 3   6  
8070Cdrom RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors 3   6  

3.03 Sodium-cooled Fast Reactors (SFR)-II
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Jean-Pol Serpanti, AREVA NP; 10 rue Juliette Recamier, ; LYON, F-69456 LYON CEDEX 06 France; Ph: 33 (0) 4 72 59 02 17 FAX: E-mail: jeanpol.serpantie@areva.com
Eric Loewen, GE Hitachi Nuclear Energy; , ; , USA; Ph: FAX: E-mail: eric.loewen@ge.com
8150Cdrom Design Studies of Large-Scale Sodium-Cooled TRU Burner 3   2  
8157Cdrom Inherent Safety Evaluation of Pool-type Liquid Metal Fast Reactors by a Multidimensional Thermal-hydraulic Calculation 3   6  
8379Cdrom Global Cooperation and Conceptual Design ARR and Recycling Strategy 3   7  
8374Cdrom An Assessment of Annular Fuel for Sodium-Cooled Fast Reactors 3   7  

3.03 Sodium-cooled Fast Reactors (SFR): The Japanese Program
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
Jean-Pol Serpanti, AREVA NP; 10 rue Juliette Recamier, ; LYON, F-69456 LYON CEDEX 06 France; Ph: 33 (0) 4 72 59 02 17 FAX: E-mail: jeanpol.serpantie@areva.com
8226Cdrom Development of Advanced Loop-Type Fast Reactor in Japan (1): Current Status of JSFR Development 3-SFR-Japan    
8231Cdrom Development of Advanced Loop-Type Fast Reactor in Japan (2): Technological Feasibility of Two-Loop Cooling System in JSFR 3-SFR-Japan   12  
8227Cdrom Development of Advanced Loop-Type Fast Reactor in Japan (3): Easy Inspection and High Reliable Reactor Structure in JSFR 3-SFR-Japan    
8223Cdrom Development of Advanced Loop-Type Fast Reactor in Japan (4): An Advanced Design of the Fuel Handling System for the Enhanced Economic Competitiveness 3-SFR-Japan    
8224Cdrom Development of Advanced Loop-Type Fast Reactor in Japan (5): Adoption of Self-Actuated Shutdown System to JSFR 3-SFR-Japan    
8082Cdrom Development of Advanced Loop-Type Fast Reactor in Japan (6) Minor Actinide Containing Oxide Fuel Core Design Study for the JSFR 3-SFR-Japan    

3.03 Sodium-cooled Fast Reactors (SFR): The French Program
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Eric Loewen, GE Hitachi Nuclear Energy; , ; , USA; Ph: FAX: E-mail: eric.loewen@ge.com
Jean-Pol Serpanti, AREVA NP; 10 rue Juliette Recamier, ; LYON, F-69456 LYON CEDEX 06 France; Ph: 33 (0) 4 72 59 02 17 FAX: E-mail: jeanpol.serpantie@areva.com
8136Cdrom Studies on French SFR Advanced Core Designs 3-SFR-French   11  
8107Cdrom Innovative Steam Generator Concepts for Sodium Fast Reactors 3-SFR-French    
8096Cdrom Sodium Fast Reactor Concepts 3-SFR-French    
8037Cdrom The Use of Gas Based Energy Conversion Cycles for Sodium Fast Reactors 3-SFR-French    

3.04 Lead-cooled Fast Reactors (LFR)-I
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
James J. Sienicki, ANL; 9700 South Cass Avenue, Building 208 ; Argonne, Illinois 60439 USA; Ph: (630) 252-4848 FAX: (630) 252-4780 E-mail: sienicki@anl.gov
Stefano Monti, ENEA; ENEA - Via Martiri di Monte Sole, 4, ; Bologna, 40129 Italy; Ph: 39.051.6098.462 FAX: 39.051.6098.785 E-mail: monti@bologna.enea.it
8073Cdrom Scoping Investigation into Viability of a Lead-Cooled Fast Reactor Demonstration Test Reactor (Demo) 3   12  
8115Cdrom A Design and Safety Features of Small CANDLE Fast Reactor 3   11  
8149Cdrom Nuclear Safety Evaluation of a LBE Cooled Transmutation Reactor, PEACER-300 3   11  
8311Cdrom Development of Transportable Capsule Version of PEACER Design 3.04    

3.04 Lead-cooled Fast Reactors (LFR)-II
THURSDAY, JUNE 12 1:00 P.M. - 3:00 P.M.
James J. Sienicki, ANL; 9700 South Cass Avenue, Building 208 ; Argonne, Illinois 60439 USA; Ph: (630) 252-4848 FAX: (630) 252-4780 E-mail: sienicki@anl.gov
Stefano Monti, ENEA; ENEA - Via Martiri di Monte Sole, 4, ; Bologna, 40129 Italy; Ph: 39.051.6098.462 FAX: 39.051.6098.785 E-mail: monti@bologna.enea.it
8331Cdrom Design and Analysis of 900 MWt Lead-Cooled Fast Reactor 3   11  
8309Cdrom A 2400 MWth Liquid Lead-Cooled Flexible Conversion Ratio (FCR) Reactor 3    
8218Cdrom Corrosion Test of Cr- and Al-containing Alloys in Static LBE at 550 C 3   8  
8029Cdrom Comparison of the Hydraulics in Concentric and Three Feeder XT-ADS Windowless Spallation Target Designs 3   6  
8003Cdrom Application of a Controlled Swirl in the XT-ADS Spallation Target 3   6  

3.06 Supercritical Water-cooled Reactor (SCWR)-I
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
X. Cheng, IKET/FZK; , ; , Germany; Ph: FAX: E-mail: Xu.Cheng@iket.fzk.de
8247Cdrom Progress within the European Project High Performance Light Water Reactor Phase 2 (HPLWR Phase 2) 3    
8100Cdrom Coolant Mixing in the Plenum of the HPLWR Three Pass Core 3   1  
8053Cdrom Determination of Mixing Coefficients in a Wire-Wrapped HPLWR Fuel Assembly using CFD 3   1  
8339Cdrom Numerical Simulation of a HPLWR Fuel Assembly Flow with Wrapped Wire Spacers 3.   6.  

3.06 Supercritical Water-cooled Reactor (SCWR)-II
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Joerg Starflinger, FZK; Forschungszentrum Karlsruhe GmbH, IKET, Bldg. 420 Hermann-von-Helmholtz-Platz 1; , ; Ph: FAX: E-mail: joerg.starflinger@iket.fzk.de
8050Cdrom Thermo-Mechanical Stress and Deformation Analysis of a HPLWR Pressure Vessel and Steam Plenum 3   1  
8076Cdrom Coupling Analysis on a New SCWR Core Design 3    
8078Cdrom Prediction of Overheated Zones along the Wall of Strongly Heated Quasi-Fully Developed Pipe Flow at Supercritical Pressure 3   1  
8336Cdrom Summary for Three Different Validation Cases of Water Coolant Flow in Supercritical Water Test Sections with the Code ANSYS CFX 11.0 3.   6.  

3.07 Molten- and Liquid-salt-cooled Reactors
THURSDAY, JUNE 12 1:00 P.M. - 3:00 P.M.
Charles Forsberg, MIT; Room 24-207A, 77 Massachusetts Avenue ; Cambridge, MA 02139 USA; Ph: (617)324-4010 FAX: E-mail: cforsber@mit.edu
8315Cdrom Reactor Physical Program in the Frame of the MSR-SPHINX Transmuter Concept Development 3   12  
8026Cdrom Design Options for the Advanced High-Temperature Reactor 3   2  
8108Cdrom Use of a Liquid Salt Nuclear Reactor to Transmute Minor Actinides 3   7  
8025Cdrom Designing the Advanced High-Temperature Reactor for Low Radionuclide Releases in a Beyond-Design-Basis Accidents 3   2  

3.08 Innovative/Advanced Power Conversion System-I
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
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
8266Cdrom Initial Status and Test Results from a Supercritical CO2 Brayton Cycle Test Loop 2   3  
8131Cdrom Design of Small Centrifugal Compressor Test Model for a Supercritical CO2 Compressor in the Fast Reactor Power Plant 3   12  
8257Cdrom Dynamic Modeling of the S-CO2 Recompression Cycle 2   6  
8203Cdrom Controllability of the Supercritical Carbon Dioxide Brayton Cycle near the Critical Point 3   12  

3.08 Innovative/Advanced Power Conversion System-II
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
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
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
8347Cdrom Supercritical CO2 Brayton Cycle Compression and Control Near the Critical Point 6   2  
8372Cdrom Comparative Analysis of Supercritical CO2 Power Conversion System Control Schemes 6   3  
8169Cdrom Preliminary Design of a Turbomachinery for the Supercritical Carbon Dioxide Brayton Cycle Coupled to the KALIMER-600 3   6  
8343Cdrom Dynamic System Analysis of a Supercritical CO2 Compression Loop 6   3  

Up

4.00: Operation, Performance & Reliability Management
Elliott Flick, Exelon Nuclear; 200 Exelon Way, ; Kennett Square, PA 19350 USA; Ph: (610)765-5910 FAX: E-mail:elliott.flick@exeloncorp.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
Gilles Monet, AREVA NP; Communications Manager, Services Sector, ; , France; Ph: FAX: E-mail:gilles.monet@areva.com

4.01 Digital I&C for New Reactors-I
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Edward Quinn, GE-Hitachi Nuclear Energy; New Units Engineering, ; , USA; Ph: (949) 632-1369 FAX: E-mail: edward.quinn@ge.com
8418Cdrom Instrumentation and Control and Human Machine Interface Science and Technology Roadmap in Support of Advanced Reactors and Fuel Programs in the U.S. 4.01    
8400Cdrom A Novel Approach to Modeling Single Event Upsets in Digital Microelectronic Devices 4.01    
8395Cdrom Licensing of Simple Digital Devices 4.01    
8327Cdrom Switching Scheme of Data Communication Network for Safety System in Nuclear Power Plant 4    
8296Cdrom An Advanced Plant Protection System for the Shin-Kori 3&4 Nuclear Power Plant 4    

4.01 Digital I&C for New Reactors-II
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Edward Quinn, GE-Hitachi Nuclear Energy; New Units Engineering, ; , USA; Ph: (949) 632-1369 FAX: E-mail: edward.quinn@ge.com
8287Cdrom Top-Mounted Incore Instrumentation Insertion Test for Westinghouse AP1000 4   8  
8271Cdrom Design of a Software Training System for Severe Accident Mitigation of Korean Standard Nuclear Power Plants 4   5  
8148Cdrom APR1400 I&C Architecture with the Advanced Design Feature Including High Reliability and Maintainability 4   5  
8135Cdrom Strategy for Establishing Integrated I&C Reliability of Operating Nuclear Power Plants in Korea 4   5  
8016Cdrom Westinghouse AP1000 Protection & Safety Monitoring System 4.01   1  

4.03 Major Component Upgrades, Designs for Reliability, Operational Issues and Mitigation Techniques
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Seth A. Swamy, Westinghouse; , ; , USA; Ph: FAX: E-mail: swamysa@westinghouse.com
8416Cdrom SG Asset Management Model Application 4   4  
8313Cdrom An Experience in Low Temperature Stress Corrosion Cracking at Steam Generator Coldleg Drain Nozzle for YGN 3 Unit 4   8  
8005Cdrom Fatigue Crack Growth Impact on Leak-Before-Break Due to Mechanical Stress Improvement Process 4   8  
8001Cdrom Effect of Structural Weld Overlay on Recommended Leak-Before-Break Margins 4   8  

4.04 Equipment Availability, Preventive Maintenance, Optimization and Best Practices-I
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Ken Ferguson, Ivara; 5046 Mainway, ; Burlington , Ontario, L7L 5Z1 Canada; Ph: (803) 642-0273 FAX: E-mail: fergkl@earthlink.net
8386Cdrom Technology Success: Integration of Power Plant Reliability and Effective Maintenance 4    
8304Cdrom Reliability Database Development and Plant Performance Improvement Effort at Korea Hydro & Nuclear Power Co. 4   5  
8164Cdrom Risk-Informed Assessment of the Scope and Frequency of Technical Service and Repair at the Kozloduy Nuclear Power Plant 4   5  

4.04 Equipment Availability, Preventive Maintenance, Optimization and Best Practices-II
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Ken Ferguson, Ivara; 5046 Mainway, ; Burlington , Ontario, L7L 5Z1 Canada; Ph: (803) 642-0273 FAX: E-mail: fergkl@earthlink.net
8168Cdrom Risk-Informed Assessment of the Scope and Frequency of Testing at the Kozloduy Nuclear Power Plant 4   5  
8042Cdrom Application of Systems Engineering to Nuclear Power Plant Design 4   13  
8015Cdrom Passing of Reactors WWER-1000 of NPP Kozloduy Bulgaria to Extended Fuel Cycle Operation (Implementation of 235U Higher Enriched Fuel) 4   1  

Up

5.00: Plant Safety Assessment and Regulatory Issues
Sandra Sloan, AREVA NP; 3315 Old Forest Road, Lynchburg, VA 25406 ; , USA; Ph: 434-832-2369 FAX: E-mail:sandra.sloan@areva.com
Christian Clment, Unistar; , ; , ; Ph: FAX: E-mail:Christian.Clement@unistarnuclear.com
Nam Dinh, Idaho National Laboratory; , ; , USA; Ph: 208-526-2242 FAX: E-mail:nam.dinh@inl.gov
Tim Haste, PSI; Paul Scherrer Institute, ; 5232 Villigen PSI, Switzerland; Ph: 41 56 310 2764 FAX: 41 56 310 4481 E-mail:tim.haste@psi.ch
Takeshi Morita, JAPC; , ; , Japan; Ph: FAX: E-mail:takeshi-morita@japc.co.jp

5.01 LOCA & non-LOCA Plant Analysis and Methodologies-I
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Tim Haste, PSI; Paul Scherrer Institute, ; 5232 Villigen PSI, Switzerland; Ph: 41 56 310 2764 FAX: 41 56 310 4481 E-mail: tim.haste@psi.ch
8376Cdrom Assessment of Core Cooling Capability of Emergency Core Cooling System in LBLOCA Condition for TAPS#3&4 5    
8258Cdrom Large Break LOCA Analysis for TAPS-3&4 Using RELAP-5/MOD 3.2 5    
8251Cdrom Large Break Loss of Coolant Accident Analysis of VVER-1000 Reactor Using CATHARE Code 5.   6.  

5.01 LOCA & non-LOCA Plant Analysis and Methodologies-II
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Donna Post Guillen, INL; Idaho National Laboratory, P.O. Box 1625 MS 3730; Idaho Falls, ID 83406 USA; Ph: 208-526-1744 FAX: E-mail: Donna.Guillen@inl.gov
Mark Drucker, Southern California Edison; SONGS Mesa W49 , P.O. Box 128 ; San Clemente, CA 92674 USA; Ph: 949-368-3997 FAX: E-mail: mark.drucker@sce.com
8260Cdrom Assessment on the Integrity of Component Cooling Water System during DBA with LOOP for Kori 3,4 Unit 5   5  
8195Cdrom Improvement of the Interfacial Drag Model in TRAC-PF1/IBER to Simulate Downcomer Boiling Phenomena 5    
8051Cdrom Sensitivity Studies on Uncertainty Parameters and Code Modeling during LBLOCA 5   6  
8314Cdrom Evaluation of Radiological Effects of the Injection of Argon Gases into Reactor Coolant System 7   9  

5.02 Development in Severe Accident Analysis, Codes and Management-I
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Eric Williams, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2779 FAX: E-mail: Eric.Williams@areva.com
8383Cdrom Dynamic Structural Analysis Concerning Integrity Assessment of a Reinforced Concrete Ceiling due to Impact Loads 9    
8295Cdrom Effect of Break Size on Severe Core Damage Behavior for VVER1000 Reactor with the ASTEC V1 Code 5    
8200Cdrom MAAP4.0.7 Analysis for PRA Level 1 Mission Success Criteria 5   6  
8201Cdrom MAAP4.0.7 Severe Accident Source Term Analysis 5   6  
8064Cdrom Analysis of Station Blackout in the Gsgen Nuclear Plant 5   6  
8063Cdrom SCDAP/RELAP5 Investigation on Coolability of Severely Degraded CANDU 6 Core Preliminary Results 5   6  

5.02 Development in Severe Accident Analysis, Codes and Management-II
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Eric Williams, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2779 FAX: E-mail: Eric.Williams@areva.com
Sama Bilbao y Leon, IAEA; Nuclear Power Technology Development Section, Wagramer Strasse 5, PO Box 100, A2569 ; 1400 Vienna, Austria; Ph: 43 (1) 2600-22865 FAX: 43 (1) 2600-29598 E-mail: S.Bilbao@iaea.org
8198Cdrom Relevant Scenarios and Uncertainty Analysis of Severe Accidents in the U.S. EPR 5   6  
8197Cdrom Recent Revisions to MAAP4 for U.S. EPR Severe Accident Applications 5   6  
8183Cdrom AREVA NP's Severe Accident Safety Issue Resolution Methodology for the U.S. EPR 5   6  
8006Cdrom Influence of Jet Breakup Modeling on Ex-Vessel Steam Explosion Simulation Results 5   6  

5.02 Development in Severe Accident Analysis, Codes and Management-III
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Robert P. Martin, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2319 FAX: E-mail: robertp.martin@areva.com
8409Cdrom Modeling of Two-Phase Natural Circulation in a Water Pool with Decay-Heated Debris Bed 5   6  
8328Cdrom Thermodynamic Analysis for the Melt Pool Configuration during the Severe Accidents in the APR1400 5   6  
8140Cdrom Transient Conduction Heat Transfer Modelling in Concrete for the Simulation of Long Term Phase of Molten Core Concrete Interaction 5    
8052Cdrom Interaction between Molten Corium UO2+x - ZrO2- FeOy and VVER Vessel Steel 5   1 or 8  
8047Cdrom European Research on the Corium Issues within the SARNET Network of Excellence 5   1  

5.03 Severe Accident Phenomena Experiment and Modeling-I
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Markus Nie, AREVA NP; , ; , Germany; Ph: FAX: E-mail: markus.nie@areva.com
8065Cdrom Pre-Test Calculational Support for the QUENCH-13 Experiment 5   6  
8390Cdrom An Experimental Study on Debris Formation with Corium Simulant Materials 5   1  
8123Cdrom An Investigation on the Material Effect on the Result of Fuel Coolant Interaction in the TROI Experiments 5    
8069Cdrom Comparison of the High Temperature Steam Oxidation Kinetics of Advanced Cladding Materials 5   8  

5.03 Severe Accident Phenomena Experiment and Modeling-II
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Joy L. Rempe, Idaho National Laboratory; P.O. Box 1625, MS 3840, ; Idaho Falls , Idaho 83415-3840 USA; Ph: 208-526-2897 FAX: 208-526-2930 E-mail: joy.rempe@inl.gov
8141Cdrom Towards a Comprehensive Interpretation of 2D MCCI Tests 5    
8281Cdrom Measurements of the Mechanical Strength of Corium Crusts 5    
8059Cdrom Differences between Silica and Limestone Concretes that may Affect their Interaction with Corium 5   8  
8058Cdrom Current European Experiments on 2D Molten Core Concrete Interactions: HECLA and VULCANO 5    
8098Cdrom Interpretation of Real Material 2D MCCI Experiments in Homogeneous Oxidic Pool with the ASTEC/MEDICIS Code 1   5  

5.03 Severe Accident Phenomena Experiment and Modeling-III
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Karen Vierow, Texas A&M University; , ; College Station, TX USA; Ph: 979-458-0600 FAX: E-mail: vierow@ne.tamu.edu
8308Cdrom Application of the ASTEC V1 Code to the LIVE-L1 Experiment 5   6  
8116Cdrom Experimental and Post-Test Calculation Results of the Integral Reflood Test QUENCH-12 with a VVER-Type Bundle Track 5:    
8086Cdrom Direct Containment Heating Experiments for Konvoi Power Plants 5    
8032Cdrom Triggered Steam Explosions with Corium Melts of Various Compositions in a Narrow Interaction Vessel in the TROI Facility 5    

5.04 Development in Life Extension Issues and Advances in Regulatory Safety Assessment-I
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Christian Clment, Unistar; , ; , ; Ph: FAX: E-mail: Christian.Clement@unistarnuclear.com
Takeshi Morita, JAPC; , ; , Japan; Ph: FAX: E-mail: takeshi-morita@japc.co.jp
8351Cdrom A Study on the Operator's Communication Pattern Characteristics under Abnormal Operating Situation of Nuclear Power Plants 5.05    
8176Cdrom Mechanism-based Ageing Management of Primary Water Stress Corrosion Cracking of Ni-base Components in PWR Environments 5   8  
8114Cdrom A Study on the Verification and Validation of Programmable Logic Component in A Nuclear Power Plant 5   4  
8055Cdrom U.S. NRCs Generic Issues Program 13   5  

5.04 Development in Life Extension Issues and Advances in Regulatory Safety Assessment-II
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Christian Clment, Unistar; , ; , ; Ph: FAX: E-mail: Christian.Clement@unistarnuclear.com
Takeshi Morita, JAPC; , ; , Japan; Ph: FAX: E-mail: takeshi-morita@japc.co.jp
8085Cdrom Korean Experience in Periodic Safety Reviews and Safety Improvements of Operating Nuclear Power Plants 5    
8080Cdrom Introduction of Regulatory Guide on Cyber Security of I&C Systems in Nuclear Facilities 5   13  
8035Cdrom Resolution of Digital Instrumentation and Control and Human Factors Technical and Regulatory Issues for New Plants and for Modernization of Operating Plants 5   13  

5.05 PRA and Risk Informed Decision Making: Methodology and Advances in Practice
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Amy Slaga, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2556 FAX: E-mail: amy.slaga@areva.com
8342Cdrom Treatment of Complementary Events in Event Trees in Constructing Linked Fault Trees for Level 1 and Level 2 PRA 5    
8301Cdrom Spatial Interactions Database Development for Effective Probabilistic Risk Assessment 5   4  
8259Cdrom SIMPROC: Procedures Simulator for Operator Actions in NPPs 5   6  
8156Cdrom A Study on Uncertainties Evaluation in Containment Event Tree 5    

5.06 Development in Safety Analysis Methodologies for Future Plants
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Sandra Sloan, AREVA NP; 3315 Old Forest Road, Lynchburg, VA 25406 ; , USA; Ph: 434-832-2369 FAX: E-mail: sandra.sloan@areva.com
Sama Bilbao y Leon, IAEA; Nuclear Power Technology Development Section, Wagramer Strasse 5, PO Box 100, A2569 ; 1400 Vienna, Austria; Ph: 43 (1) 2600-22865 FAX: 43 (1) 2600-29598 E-mail: S.Bilbao@iaea.org
8370Cdrom The Comparison of Frequency-Consequence (F-C) Criteria in Evaluating the Risk of New or Existing Reactor 2   5  
8022Cdrom Overview of the Activities of the OECD/NEA/NSC Working Party on Nuclear Criticality Safety 13   5  
8279Cdrom Drafting and Implementation of a Practical Elimination Approach for Gen IV Nuclear Reactors 5    
8273Cdrom EFIT Reactor Simulation Coupling Neutronics/Thermal-hydraulics with the RELAP5/PARCS Code 7   5  
8061Cdrom Comparative Review of Design and Improved Safety Features of New LWR Plants 5    

Up

6.00: Thermal Hydraulic Analysis and Testing
Shripad Revankar, Purdue Univ; , ; , USA; Ph: FAX: E-mail:shripad@purdue.edu
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
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, Zachary 129 MS 3133; Collage Station , TX 77843-3133 USA; Ph: 979 845 7090 FAX: 979 845 6443 E-mail:y-hassan@tamu.edu
Genevieve Geffraye, CEA; , ; , France; Ph: FAX: E-mail:genevieve.geffraye@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
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 Best Estimate Analysis Codes and Uncertainty Methodologies-I
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
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
8248Cdrom Verification and Validation of Almaraz NPP TRACE Model 6   1  
8235Cdrom Parametric Sensitivity Study on the Reflooding Models of the MARS Code Based on 6x6 Rod Bundle Test Results 6   5  
8117Cdrom Implementation of a New Controlling Function in MELCOR Computer Code for Uncertainty Evaluations 6   4  

6.01 Best Estimate Analysis Codes and Uncertainty Methodologies-II
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
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
8394Cdrom TRACG Statistical Method for BWR Loss-of-Coolant Accident Analyses 6   5  
8387Cdrom BFBT Benchmark Sub-Channel Analysis with RELAP5-3D Code 6   1  
8375Cdrom Assessment of Compensating Error in the WCOBRA/TRAC-TF2 Thermal-Hydraulic Code 6   6  
8269Cdrom Development and Qualification of the Coupled Code System COBRA-TF/THREEDANT for the Pin-by-Pin Power Calculation 11   5  

6.02 Integral and Separate Thermal Hydraulics Testing and Analysis
TUESDAY, JUNE 10 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
8369Cdrom An Improved Horizontal Flow Regime Map for the 1-D Module of WCOBRA/TRAC-TF2 6   6  
8272Cdrom Full-size and Scaled 3-loop Reactor Vessel Simulation for Boron Dilution Studies Using CFD 6    
8189Cdrom MELCOR Validation against a PUMA Facility Main Steam Line Break Integral Test 6   5  
8129Cdrom An Integral Effect Test on the Reflood Period of a Large-Break LOCA for APR1400 Using the ATLAS 6   1  

6.03 System Simulation Models and Codes-I
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Shripad Revankar, Purdue Univ; , ; , USA; Ph: FAX: E-mail: shripad@purdue.edu
8124Cdrom Experimental Validation of a Core Heat Transfer Model in the TASS/SMR Code Using Film Boiling Data 6   1  
8119Cdrom PC-based Simulator PCTRAN for Advanced Nuclear Power Plants 6   11  
8106Cdrom Analysis of Dynamic Behavior of MEGAPIE Cooling System 6   3  
8041Cdrom Development of Evaluation System of Safety Margin Effects for Degradation of CANDU Reactors Using RELAP-CANDU 6   5  

6.03 System Simulation Models and Codes-II
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Shripad Revankar, Purdue Univ; , ; , USA; Ph: FAX: E-mail: shripad@purdue.edu
8323Cdrom Testing Programs Related to Potential Adverse Flow Effects In Nuclear Power Plants    
8262Cdrom The TRAB-SMABRE for 3D Plant Transient and Accident Analyses 11    
8179Cdrom Analysis of Beyond Design Basis Accidents in Spent Fuel Pools of the Ignalina NPP 6   9  

6.05 Advanced Reactor Testing and Analysis
THURSDAY, JUNE 12 1:00 P.M. - 3:00 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
8429Cdrom Subchannel Analysis of CANDU-SCWR Fuel 6   1  
8419Cdrom GNF2 Counter-Current Flow Limitation Testing 1   6  
8270Cdrom Interfacial Momentum Exchange Models Used in Nuclear Reactor System Analysis Codes    
8170Cdrom Thermohydrodynamic Analysis of Reactor Vessel Auxiliary Cooling System for Lead-Cooled Battery Omnibus Reactor Integral System 6   3  
8077Cdrom Development of High Fidelity System Analysis Code for GEN IV Reactors 6   3  
8012Cdrom Multidimensional Analysis of Developing Two-phase Flows in an ESBWR Chimney with and without Riser Channels 6    

6.06 Advances in Two-Phase Flow and Heat Transfer-I
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Michael A. Shockling, Westinghouse; , ; , USA; Ph: FAX: E-mail: shocklma@westinghouse.com
8391Cdrom On the Modeling of Channel-to-Channel Oscillations in Boiling Water Reactors 6   11  
8137Cdrom Heat Transfer in Intermediate Heat Exchanger under Low Flow Rate Conditions 6   4  
8121Cdrom Identification of the Relation between Turbulence Coefficient and Local Wall Thinning inside Carbon Steel Piping 6   4  
8095Cdrom Theoretical and Experimental Study of Steam Condensation Induced Water Hammer Phenomena 6   9  

6.06 Advances in Two-Phase Flow and Heat Transfer-II
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Michael A. Shockling, Westinghouse; , ; , USA; Ph: FAX: E-mail: shocklma@westinghouse.com
8286Cdrom Transient Accident Analysis of the Glovebox System in a Large Process Room 6   5  
8275Cdrom Pressure Drop Characteristics of Cross-Shaped Spiral (CSS) Rod Bundle for LWRs 6   1  
8225Cdrom Application of the Subchannel Analysis Code MATRA for Low Flow and Low Pressure Conditions 6   1  
8209Cdrom Optimizing Critical Heat Flux Enhancement through Nanoparticle-Based Surface Modifications 6   1  

6.06 Advances in Two-Phase Flow and Heat Transfer-III
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Meghan E. Leslie, Westinghouse; , ; , USA; Ph: FAX: E-mail: leslieme@westinghouse.com
8043Cdrom Applications of Nanofluids to Enhance LWR Accidents Management in In-vessel Retention and Emergency Core Cooling System 1   6  
8330Cdrom Thermal-fluid Characterization of ZnO Nanofluid for Advanced Nuclear Power Plants 6   1  
8292Cdrom Evaluation of Crack Opening Area, Leak Rate and Probabilistic Models in CANTIA 6   6  
8290Cdrom Condensation Correlation for a Vertical Passive Condenser System 6   6  

6.07 CFD Applications to Water, Liquid Metal and Gas Reactors-I
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Si Young Lee, Savannah River National Lab. ; Computational and Statistical Science Dept. , ; Aiken, SC 29808 USA; Ph: 803-725-8462 FAX: E-mail: si.lee@srnl.doe.gov
8127Cdrom Pressure Loss Coefficient Evaluation Based on CFD Analysis for Simple Geometries and PWR Reactor Vessel without Geometry Simplification 6   6  
8122Cdrom CFD Estimation of the Heat Transfer due to the Natural Convection in a CEA Extension Shaft Guide Tube 6    
8094Cdrom System / CFD Coupling for Reactor Transient Analysis. An Application to the Gas Fast Reactor with CATHARE and TRIO_U 6   3  
8062Cdrom A CFD Solver with Variable Gas Properties for Applications to High Temperature Gas Cooled Reactors 6    
8049Cdrom Free Surface Modeling and Simulation of the Water Experiment for the XT ADS Spallation Target 6    

6.07 CFD Applications to Water, Liquid Metal and Gas Reactors-II
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Anne Charmeau, Univ of Florida; , ; , USA; Ph: FAX: E-mail: anne@inspi.ufl.edu
8264Cdrom CFD Calculations of the Assembly of VVER-440 type PWR Reactors 6   1  
8252Cdrom RANS-based CFD Simulations of Wire-Wrapped Fast Reactor Fuel Assemblies 6   3  
8155Cdrom CFD Predictions of Heat Transfer in the Super Critical Flow Regime 6    

6.07 CFD Applications to Water, Liquid Metal and Gas Reactors-III
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Yassin Hassan, Texas A & M University; Dept. of Nuclear Engineering, Zachary 129 MS 3133; Collage Station , TX 77843-3133 USA; Ph: 979 845 7090 FAX: 979 845 6443 E-mail: y-hassan@tamu.edu
8278Cdrom Study on Coolant Mixing in VVER-440 Fuel Assembly Head 6    
8265Cdrom Evaluation of the Two-phase Flow Characteristics in the Steam Separator by Using a CFD Code 6   1  
8212Cdrom k-ε Modeling Using Modified Nodal Integral Method 6    

6.08 Thermal Hydraulics Measurement and Modeling Fundamentals-I
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
Seungjin Kim, The Pennsylvania State Univ; 230 Reber Building, ; University Park, PA 16802 USA; Ph: (814) 867-1783 FAX: (814) 865-8499 E-mail: skim@psu.edu
8333Cdrom Supercritical Water Heat Transfer in a Vertical Bare Tube: Normal, Improved and Deteriorated Regimes 6   1  
8303Cdrom LWR Containment Safety Research in PANDA 6    
8229Cdrom Interfacial Area Transport in Horizontal Bubbly Flow with Elbow Restrictions 6    
8222Cdrom High Temperature Irradiation Resistant Thermocouples A Low Cost Sensor for In-Pile Testing at High Temperatures 6   8  
8151Cdrom Analysis of Two-Phase Flow and Boiling Heat Transfer in Inclined Channel of Core-catcher 6    
8441Cdrom Performance and Scaling Analysis for the Two-Phase Natural Circulation 6.08a    

6.08 Thermal Hydraulics Measurement and Modeling Fundamentals-II
THURSDAY, JUNE 12 1:00 P.M. - 3:00 P.M.
Seungjin Kim, The Pennsylvania State Univ; 230 Reber Building, ; University Park, PA 16802 USA; Ph: (814) 867-1783 FAX: (814) 865-8499 E-mail: skim@psu.edu
8306Cdrom Development of the Cooling Technology on TRU Fuel Pin Bundle during Fuel Fabrication Process (1) Whole Study Plan and Fabrication of Test Apparatuses 6   3  
8310Cdrom Development of the Cooling Technology on TRU Fuel Pin Bundle during Fuel Fabrication Process (2) High-Speed PIV Measurements in Gap among Fuel Pins 6   3  
8316Cdrom Development of the Cooling Technology on TRU Fuel Pin Bundle during Fuel Fabrication Process (3) Development of Analytical Tool 6   3  
8332Cdrom An Assessment of Large-Eddy Simulation for Thermal Fatigue Prediction 6    
8329Cdrom Experimental Investigation of Crud Deposition under Sub-cooled Boiling Conditions 6    

6.09 Thermal Hydraulics of Gas-Cooled Reactor Systems
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
Genevieve Geffraye, CEA; , ; , France; Ph: FAX: E-mail: genevieve.geffraye@cea.fr
8322Cdrom Investigation of Heat Transfer for Gas Cooled Systems 2   6  
8146Cdrom Mixing Process by Natural Convection and Molecular Diffusion of Two Component Gases in a Stable Stratified Fluid Layer 6   2  
8009Cdrom Design Considerations For Compact Heat Exchangers 6   2  

Up

7.00: Fuel Cycle and Waste Management
Temitope Taiwo, ANL; , ; , USA; Ph: FAX: E-mail:Taiwo@ANL.gov
Dominique Greneche, AREVA NC; 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:dominique.greneche@areva.com
Chan Oh Park, KEPCO Nuclear Fuel Co. (KNFC); , ; , Korea; Ph: FAX: E-mail:copark@knfc.co.kr
Toshikazu Takeda, Osaka University; , ; , Japan; Ph: FAX: E-mail:takeda@nucl.eng.osaka-u.ac.jp

7.01 Strategies for Advanced Fuel Cycles
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Toshikazu Takeda, Osaka University; , ; , Japan; Ph: FAX: E-mail: takeda@nucl.eng.osaka-u.ac.jp
8102Cdrom A Contingency Safe, Responsible, Economic, Increased Capacity Spent Nuclear Fuel (SNF) Disposition to Avoid Interference with Yucca Mountain Licensing 7    
8046Cdrom Market Share Scenarios for Gen-III and Gen-IV Reactors in Europe 7   9  
8089Cdrom Progress in Development of Erbia-Bearing Super High Burnup Fuel 7   11  

7.02 Spent Fuel Recycling Technologies-I
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Dominique Greneche, AREVA NC; 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: dominique.greneche@areva.com
8284Cdrom Radioactive Waste Management in Romania 7    
8101Cdrom Prospects of Thorium - Fuel Reprocessing for Molten Salt Reactor Systems 7   3  
8014Cdrom A Study on Methodology of Optimal Characterization and Disposal Priority for Low and Intermediate Level Radioactive Wastes (LILWs) in Korea 7    
8208Cdrom Development of an Integrated Systems Engineering Modeling Package for Chemical Separation Processes under Advanced Fuel Cycle Initiative 7    

7.02 Spent Fuel Recycling Technologies-II
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Dominique Greneche, AREVA NC; 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: dominique.greneche@areva.com
8165Cdrom Development of FR Fuel Cycle in Japan (1) - Development Scope of Fuel Cycle Technology 7   3  
8161Cdrom Development of FR Fuel Cycle in Japan (2) Basic Design and Verification of U-Pu-Np Co-recovery Flowsheets for Engineering Scale Hot Examination in Japan 7    
8142Cdrom Development of FR Fuel Cycle in Japan (3) - Current State on Unified Technology of Denitration Conversion and Granulation for Simplified Pellet Fuel Fabrication Based on Microwave Heating 7    
8236Cdrom Development of FR fuel cycle in Japan (4) Consideration of Transition from LWR-cycle to FR-cycle 7    

7.03 Advanced Fuel Cycles, Recycling, and Actinide Transmutation
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Temitope Taiwo, ANL; , ; , USA; Ph: FAX: E-mail: Taiwo@ANL.gov
8171Cdrom Evaluation of the Possibility of Plutonium and Minor Actinides Transmutation in HWR 7    
8174Cdrom Preliminary Analysis by Means of the TRANSURANUS Code of Mixed Oxide Fuel Rod for Gen IV Lead Fast Reactor 7   3  
8033Cdrom Mixed Plutonium Conversion and Actinides Burning in Fast Molten Salt Reactors 7    

Up

8.00: Materials and Structural Issues
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
Jim Cole, INL; PO Box 1625, MS 6188 ; Idaho Falls, ID 83403 USA; Ph: 208-533-7165 FAX: E-mail:jim.cole@inl.gov
Ram Srinivasan, AREVA; 6399 San Ignacio Ave., ; San Jose, Ca 95119 USA; Ph: 408 513 3544 FAX: 434 382 5387 E-mail:ram.srinivasan@areva.com
Franoise 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
Woo-Seog Ryu, KAERI; , ; , Korea; Ph: FAX: E-mail:wsryu@kaeri.re.kr
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 Analysis and Design
TUESDAY, JUNE 10 10:00 A.M. - 12:00 P.M.
Franoise 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
Ram Srinivasan, AREVA; 6399 San Ignacio Ave., ; San Jose, Ca 95119 USA; Ph: 408 513 3544 FAX: 434 382 5387 E-mail: ram.srinivasan@areva.com
8321Cdrom New Nuclear Power Plants in Europe - Design Aspects for Constructural Engineering 8.01   5  
8210Cdrom Multiscale Modeling Approach to Stress Corrosion Cracking 8   11  
8181Cdrom Influence of Non Linear Geometrical Parameter on Curved Thin Shell Buckling Behaviour 8    
8152Final Missile Impact on Reinforced Concrete Slabs: Three Dimensional Dynamic Finite Element Analysis 8   5  

8.02 Materials and Structures Testing-I
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 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
8399Cdrom Correlation between Intrinsic Hardness and Defect Structures of Ion Irradiated Fe Alloys 8    
8297Cdrom Dynamics of Frictional Interaction of a Fuel Rod Cladding and Spacer Grid Cell in a Fuel Assembly 7    
8239Cdrom Ultrasonic TOFD Method Application for Steel Components and Welds of 10mm Wall Thickness Using Digital Ultrasonic Flaw Detector and ULTRA 7- TOFD Software 8    
8044Cdrom Study of the Tunneling Effect within Lattices with Cubic Structure on Varying Temperature 10   11  

8.02 Materials and Structures Testing-II
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 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
8220Cdrom High Temperature Material Properties for Metals used in LWR Vessels 8    
8186Cdrom Flaw Tolerance Evaluation to Support Alternative Examination Volume and/or Inspection Interval for Nickel-Based Alloy Components 4    
8057Cdrom Oxide Fouling Mitigation Technology in BWR 8    
8020Cdrom Flexural Behavior of Concrete Beam with Mechanical Splices of Reinforcement Subjected to Cyclic Loading 8   4  

8.04 Materials Issues for Next Generation NPP: Environment
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 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
Woo-Seog Ryu, KAERI; , ; , Korea; Ph: FAX: E-mail: wsryu@kaeri.re.kr
8060Cdrom Creep Behaviors of Alloy 617 at Temperatures between 800 and 1000oC 8   2  
8163Cdrom Corrosion Studies of Candidate Materials for European HPLWR 8    
8048Cdrom Theoretical Design of SCC Resistant Ni-base Alloy by Computational Chemistry Approach 8   1  

8.05 Materials Issues for Next Generation NPP: Structural Mechanics
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
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
8307Cdrom Study on an Innovative Fast Reactor Utilizing Hydride Neutron Absorber 8   3  
8261Cdrom Comparison of Inelastic Behaviors Between Cold Worked 316L and Solution Annealed 316L Stainless Steels 8   3  
8230Cdrom Effects of Alloying Elements on Microstructure and Mechanical Properties in SA508 Gr.4N Low Alloy Steel 8   8  
8166Cdrom Effects of Welding on Toughness of Mod.9Cr-1Mo Steel 8   2  
8019Cdrom Development of Digital Materials Database for Design and Construction of New Power Plants 8    

Up

9.00: Nuclear Energy and Sustainability
J. Stephen Herring, INL; , ; , USA; Ph: FAX: E-mail:j.herring@inl.gov
Tom Mulford, Electric Power Research Institute ; , ; Palo Alto, CA 94304 USA; Ph: FAX: E-mail:TMULFORD@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
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

9.01 Sustainability: International
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Tom Mulford, Electric Power Research Institute ; , ; Palo Alto, CA 94304 USA; Ph: FAX: E-mail: TMULFORD@epri.com
8430Cdrom IAEAs Study of Advanced Applications of Water Cooled Nuclear Power Plants 9    
8111Cdrom Analytical Hierarchy Process for the Selection of Nuclear Reactors for Mexico 9    
8013Cdrom New Power Expansion Strategy and Low GHG Emitting Economy in Korea 9   10  
8087Cdrom The Role of Nuclear Power in CO2 Emission Reduction in Korea 9   9  
8312Cdrom Evaluation of the Scenario for Innovative Russian Nuclear Power Development 9   3  

9.01 Sustainability: Applications
MONDAY, JUNE 9 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
8038Cdrom Risks and Benefits of Nuclear Energy in a Sustainable Development Perspective 9    
8427Cdrom The Norwegian Thorium Initiative 9    
8024Cdrom High-Temperature Reactors for Underground Liquid Fuels Production with Direct Carbon Sequestration 9   2  
8319Cdrom Novel Reactor Designs to Burn Non-Fissile Fuels 12   3  

9.02 Hydrogen Production
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
Carl Stoots, INL; , ; , USA; Ph: FAX: E-mail:
Theron Marshall, INL; , ; , USA; Ph: FAX: E-mail: Theron.Marshall@inl.gov
8245Cdrom Initial Operation of the High Temperature Electrolysis Integrated Laboratory Scale Experiment at INL 9   2  
8244Cdrom Commercial Scale Performance Predictions for High-Temperature Electrolysis Plants Coupled to Three Advanced Reactor Types 9   2  
8125Cdrom Hydrogen Production for Transportation Fuels Using Nuclear Energy 9   2  
8373Cdrom Initial Assessment of the Operability of the VHTR-HTE Nuclear Hydrogen Plant 9   2  
8039Cdrom Oncethrough Hybrid Sulfur Process for Nuclear Hydrogen Production 9   2  
8443Cdrom Integrating Large-Scale Co-Generation of Hydrogen and Electricity from Wind and Nuclear Sources (NUWIND™)    

Up

10.00: Near Term Issues
Jeffrey F. Hamel, Electric Power Research Institute ; 3420 Hillview Avenue , ; Palo Alto, CA 94304 USA; Ph: 650.855.2095 FAX: E-mail:jhamel@epri.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
Alain Calamand, AREVA NP; 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@areva.com

10.01 Near Term Issues-I
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Jeffrey F. Hamel, Electric Power Research Institute ; 3420 Hillview Avenue , ; Palo Alto, CA 94304 USA; Ph: 650.855.2095 FAX: E-mail: jhamel@epri.com
8438Cdrom Integration of New Nuclear Plants into the Grid, Part I: Transmission System Issues 10    
8442Cdrom Integration of New Nuclear Power Plants into Transmission Grids, Part II: Zones of Vulnerabilities (ZoV)    
8340Cdrom Advanced Cooling Technologies 10    
8318Cdrom Application of Hybrid Cooling Technology for North Anna Unit 3 10    

10.01 Near Term Issues-II
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Jeffrey F. Hamel, Electric Power Research Institute ; 3420 Hillview Avenue , ; Palo Alto, CA 94304 USA; Ph: 650.855.2095 FAX: E-mail: jhamel@epri.com
8422Abs.a Future Nuclear Power Potential and Characteristics in Developing Countries 10    
8337Abs.a Common User Considerations (CUC) by Developing Countries for Future Nuclear Power Plants 10    
8068Cdrom Human Resource Development for New Nuclear Power Plant Unit in Armenia 10   13  

10.01 Near Term Issues-III
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Jeffrey F. Hamel, Electric Power Research Institute ; 3420 Hillview Avenue , ; Palo Alto, CA 94304 USA; Ph: 650.855.2095 FAX: E-mail: jhamel@epri.com
8040Cdrom Near-Term Deployment of Advanced Light Water Reactors 10   10  
8380Cdrom How an EAM Solution Could Support a New Build Project? 4   5  
8067Cdrom Design of Integrated Managing System for NPP Safety Based on CIMS and Fractal Modeling Method 4   5  

Up

11.00: Reactor Physics and Analysis
Bojan Petrovic, Georgia Institute of Technology; G.W. Woodruff School of Mechanical Engineering, 771 Ferst Dr. NW, Love Bldg. Rm 020 ; Atlanta, GA 30332-0405 USA; Ph: (404) 894-8173 FAX: (404) 894-8496 E-mail:Bojan.Petrovic@gatech.edu
Russell Stachowski, Global Nuclear Fuel ; 3901 Castle Hayne Road, M/C H25 , ; Wilmington, NC 28401 USA; Ph: 910-675-5019 FAX: 910-675-6966 E-mail:russell.stachowski@gnf.com
Anne Nicolas, CEA; DEN/DANS/DM2S/SERMA, CEN Saclay ; F - 91191 Gif-sur-Yvette Cedex, France; Ph: 33 1 69 08 59 89 FAX: 33 1 69 08 94 90 E-mail:anne.nicolas@cea.fr
Christine Poinot-Salanon, CEA; CEA/Saclay - Building 470, ; 91191 Gif/Yvette, 91191 France; Ph: 33 1 69 08 53 73 FAX: 33 1 69 08 99 35 E-mail:christine.poinot@cea.fr
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
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
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
Dubravko Pevec, Univ of Zagreg; , ; , Croatia; Ph: FAX: E-mail:dubravko.pevec@fer.hr

11.01 Reactor Physics Methods, Codes and Validation
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Christine Poinot-Salanon, CEA; CEA/Saclay - Building 470, ; 91191 Gif/Yvette, 91191 France; Ph: 33 1 69 08 53 73 FAX: 33 1 69 08 99 35 E-mail: christine.poinot@cea.fr
8435Cdrom A Heterogeneous Model for Burnup Calculation in High Temperature Gas Cooled Reactors 11.01    
8246Cdrom The Enhancements and Testing for the MCNPX Depletion Capability 11    
8371Cdrom A New Method to Compute the Dominance Ratio in Monte Carlo Simulations - Application to a Simple Pin Cell with the 3-D Monte Carlo code Tripoli-4 11    
8205Cdrom Pin-by-Pin Power Reconstruction in the Future EDF Calculation Scheme 11    
8207Cdrom Element of Validation of Microscopic Depletion for the Future EDF Calculation Scheme Based on APOLLO2 and COCAGNE Codes 11    
8202Cdrom Elements of Validation of Pin-by-Pin Calculations with the Future EDF Calculation Scheme Based on APOLLO2 and COCAGNE Codes 11    

11.02 Nuclear Data, Cross-section Libraries and Validation
TUESDAY, JUNE 10 10:00 A.M. - 12:00 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
8178Cdrom ZPPR-21 Critical Benchmark Analyses with ENDF/B-V and -VII Data 11    
8118Cdrom An Application Method of Benchmark Experiment Results to Small Innovatiove Fast Reactor Designs 11   12  
8109Cdrom Development of a Test Suite for Nuclear Data Verification and Validation of Nuclear Data 11   1  
8084Cdrom Identification of the Doppler Reactivity Coefficient from a Low Power Transient Observed in a Zero-Power Reactor Physics Test of PWRs 11   4  
8028Cdrom Improvement of Prediction Accuracy for Fuel Fabrication System with Erbia Bearing Fuel 11   1  

11.03 New Reactor Core Concepts and Fuel Management
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Bojan Petrovic, Georgia Institute of Technology; G.W. Woodruff School of Mechanical Engineering, 771 Ferst Dr. NW, Love Bldg. Rm 020 ; Atlanta, GA 30332-0405 USA; Ph: (404) 894-8173 FAX: (404) 894-8496 E-mail: Bojan.Petrovic@gatech.edu
8274Cdrom Checkmate - A New Concept in Core Design 7   4  
8267Cdrom A Minimum Shuffle Core Design Strategy for ESBWR 11   11  
8159Cdrom Neutronic Study for Introduction of Erbium as a Burnable Poison into the Fuel Cladding Tube to Enable PWR Core Control 11   1  
8083Cdrom Modification of the Japanese First Nuclear Ship for a Regional Energy Supply System 11    

11.04 Reactor Physics Analyses and Applications
THURSDAY, JUNE 12 10:00 A.M. - 12:00 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
8255Cdrom Validation of Shielding Design for Spent Nuclear Fuel Cask Storage Facility Using Various Codes 5   7  
8217Cdrom Reactor Physics Aspects of the Incident Occurred at Paks NPP in 2003 5   11  
8242Cdrom Core Monitoring - Combining Measurements from Different Nuclear Instrumentations 11   4  
8234Cdrom Decay Heat Analysis of a VHTR Core using HELIOS and ORIGNE-2 Codes 11   11  
8167Cdrom Criticality Calculations on Realistic Modeling of Pebble-bed HTR-PROTEUS as a Validation for the Woodcock Tracking Method Implemented in the MORET 5 Monte Carlo Code 11    
8018Cdrom Optimal Control Search of Xenon Oscillation Control in Large PWRs Using a Characteristic Ellipse Trajectory Drawn by Three Axial Offsets 11   4  

Up

12.00: Innovative and Space Reactor Systems
Shannon Bragg-Sitton, Texas A&M University; 129 Zachry Engineering Center, 3133 TAMU , ; College Station, TX 77843-3133 USA; Ph: 979-862-8446 FAX: 979-845-6443 E-mail:sitton@tamu.edu
Thomas Larson, INL; , ; , USA; Ph: 208-526-5775 FAX: 208-526-4017 E-mail:thomas.larson@inl.gov
Norbert Frischauf, QASAR Technologie(s); MSM-ES, Keplerlaan 1 Postbus 299; NL-2200 AG Noordwijk , The Netherlands; Ph: 31 71 565 / 4910 FAX: 31 71 565 / 6024 E-mail:Norbert.Frischauf@cern.ch

12.01 Planetary Surface Power Strategy and Design
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Shannon Bragg-Sitton, Texas A&M University; 129 Zachry Engineering Center, 3133 TAMU , ; College Station, TX 77843-3133 USA; Ph: 979-862-8446 FAX: 979-845-6443 E-mail: sitton@tamu.edu
8412Cdrom Compact, Readily Deployable Reactor Systems for Secure Power for Civilian and Defense Applications 12   9  
8344Cdrom A Basic LEGO Reactor Design for the Provision of Lunar Surface Power 12   11  
8294Cdrom Modeling and Analysis of a Lunar Space Reactor with the Computer Code RELAP5-3D/ATHENA 12   6  
8254Cdrom Modifications of the Fission Surface Power Primary Test Circuit (FSP-PTC) 12   6  

12.02 Concepts for Advanced Space Systems
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
J. Boise Pearson, NASA-MSFC; XD20/Propulsion Research Center, NASA Marshall Space Flight Center ; Huntsville, AL 35812 USA; Ph: 256-961-0078 FAX: 256-544-5926 E-mail: J.Boise.Pearson@nasa.gov
8173Cdrom Experimental and Research Study of Novel Nuclear Concepts (Survey of Current Results of ISTC Programs) 0.00   12.00  
8172Cdrom Computational Thermohydrodynamic Analysis of Thermal Engine Rocket Adventurer for Space Nuclear Application 12   6  
8160Cdrom Recent Developments of the MOA Thruster, a High Performance Plasma Accelerator for Nuclear Power and Propulsion Applications 12    

12.03 Upgrading the Research Reactor Capabilities for Advanced Technology Development
WEDNESDAY, JUNE 11 10:00 A.M. - 12:00 P.M.
Trent Primm, ORNL; , ; , USA; Ph: FAX: E-mail: primmrtiii@ornl.gov
8153Cdrom Thermal Hydraulics Analysis of the MIT Research Reactor Low Enrichment Uranium (LEU) Core 6   5  
8425Cdrom Advanced Test Reactor - National Scientific User Facility: Research Proposal Process Lessons Learned 12.03    
8424Cdrom Proposed Fuel Pin Irradiation Facilities for the High Flux Isotope Reactor 12.03    
8423Cdrom Innovations in Design for the Enhancement of Experimental Neutron Flux at the Massachusetts Institute of Technology Research Reactor 12.03    
8408Cdrom The ATR National Scientific User Facility: A New Role for a National Asset 1.5    

12.04 Ground Testing and Thermionic Conversion
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Norbert Frischauf, QASAR Technologie(s); MSM-ES, Keplerlaan 1 Postbus 299; NL-2200 AG Noordwijk , The Netherlands; Ph: 31 71 565 / 4910 FAX: 31 71 565 / 6024 E-mail: Norbert.Frischauf@cern.ch
8298Cdrom General Purpose Heat Source Simulator 12   4  
8288Cdrom NaK Plugging Meter Design for the Feasibility Test Loops 12    
8193Cdrom Concept of Direct Energy Conversion Nuclear Cogeneration Plant 12    

Up

13.00: Plant Licensing Issues
John Tappert, US NRC; , ; , USA; Ph: FAX: E-mail:JRT@nrc.gov
Donna Williams, USNRC; , ; , USA; Ph: 301-415-1322 FAX: E-mail:dms6@nrc.gov
Satoru Kondo, JAEA; Japan Atomic Energy Agency (JAEA), 1 Shiraki ; Truruga-shi, Fukui-ken 919-1279 Japan; Ph: 81-770-39-1031 FAX: 81-770-39-9103 E-mail:kondo.satoru@jaea.go.jp

13.01 Multinational Regulatory Cooperation
MONDAY, JUNE 9 2:30 P.M. - 4:00 P.M.
Gary Holahan, US NRC; , ; , USA; Ph: FAX: E-mail:

13.02 Regulatory Program and Strategies for New Reactor Licensing
THURSDAY, JUNE 12 1:00 P.M. - 3:00 P.M.
Patrick Madden, US NRC; , ; , USA; Ph: FAX: E-mail:
8431Cdrom Competitive Paths to New Plant Licensing 13.05    

13.03 International Activities on Codes and Standards for New Reactor Designs - Relationship of the Regulatory and Inspection Process to Design
TUESDAY, JUNE 10 2:30 P.M. - 4:00 P.M.
Michael Mayfield, US NRC; , ; , USA; Ph: FAX: E-mail:

13.04 Regulatory Oversight of Construction
WEDNESDAY, JUNE 11 1:00 P.M. - 2:30 P.M.
Glenn Tracy, US NRC; , ; , USA; Ph: FAX: E-mail:

13.05 Key Licensing and Regulatory Issues for Gen III, III+, IV Reactors
WEDNESDAY, JUNE 11 2:30 P.M. - 4:00 P.M.
Edward Baker, US NRC; , ; , USA; Ph: FAX: E-mail:

13.06 New Reactor Siting Issues
TUESDAY, JUNE 10 1:00 P.M. - 2:30 P.M.
Nilesh Chokshi, US NRC; , ; , USA; Ph: FAX: E-mail:

13.07 Regulatory Oversight of Component Manufacturing
THURSDAY, JUNE 12 10:00 A.M. - 12:00 P.M.
Glenn Tracy, US NRC; , ; , USA; Ph: FAX: E-mail:
8325Cdrom Special Treatment for Important to Safety Structures, Systems and Components (SSCs) in the Licensing of Light Water Reactors 13    

Up

14.00: Plenary Sessions
8388Abs.r FBR Cycle Technology Development in Japan plenary    

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The last update is: Mon Nov 17 08:46:19 2008