2003 International Congress on
Advances in Nuclear Power Plants
ICAPP ’03
May 4-7, 2003 • Congress Palais • Córdoba, SPAIN
Home Organizers Call for Papers Papers/Program Highlights Hotels Córdoba Registration
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2003 International Congress on Advances in Nuclear Power Plants ICAPP ’03 May 4-7, 2003 • Congress Palais • Córdoba, SPAIN |
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Home Organizers Call for Papers Papers/Program Highlights Hotels Córdoba Registration |
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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:
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0.00: Unassigned Abstracts/Papers 1.00: Water Cooled Reactor Programs and Issues 2.00: High Temperature Gas Reactors 3.00: Future Deployment Programs and Issues 4.00: Operations, Plant Performance, and Reliability 5.00: Plant Evaluations and Safety Assessments 6.00: Thermal Hydraulic Analysis and Testing 8.00: Material and Structural Issues |
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| 3366 | Abs.r |
J. P. Py, Framatome ANP; , ; , France; Ph: 33 1 47960425 or 33 1 44837233 FAX: E-mail: jeanpierre.py@framatome-anp.com
Manuel Ibañez, UNESA; , ; , Spain; Ph: 91 – 567.48.00 FAX: E-mail: mdibanez@unesa.es
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
Bob Twilley, Framatome; , ; , USA; Ph: FAX: E-mail: bob.twilley@framatome-anp.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
Dong Wook Jerng, Korea Hydro & Nuclear Power Company (KHNP); Center for Advanced Reactors Development , NETEC, KHNP Munji-Dong 103-16 (KEPRI); Yusung-Gu, Deajon 305-380 Korea; Ph: 82-42-865-5710 FAX: 82-42-865-5704 E-mail: dwjerng@khnp.co.kr
J. P. Py, Framatome ANP; , ; , France; Ph: 33 1 47960425 or 33 1 44837233 FAX: E-mail: jeanpierre.py@framatome-anp.com
| 3318 | Cdrom | Design Rule Using North American Set of Codes and Standards for the EUR Document Safety Classification | 1 3 |
| 3249 | Cdrom | European Utility Requirements: Actions in Progress and Next Steps | 1 3 |
| 3231 | Cdrom | EPRI’s Technical Path Towards New US Nuclear Plants | 1 |
| 3210 | Cdrom | IAEA Activities in Technology Development for Advanced Water-Cooled Nuclear Power Plants | 1 |
| 3113 | Pres. | Evaluating the Viability of Future Nuclear Developments in the United States | 1 |
Dong Wook Jerng, Korea Hydro & Nuclear Power Company (KHNP); Center for Advanced Reactors Development , NETEC, KHNP Munji-Dong 103-16 (KEPRI); Yusung-Gu, Deajon 305-380 Korea; Ph: 82-42-865-5710 FAX: 82-42-865-5704 E-mail: dwjerng@khnp.co.kr
| 3059 | Cdrom | Design of the Reactor Pressure Vessel and Internals of the IRIS Integrated Nuclear System | 3 |
| 3047 | Cdrom | The Feasibility of Using a 15 MW General Atomics TRIGA Core as an Autonomous Marine Power Supply (AMPS) |
| 3228 | Cdrom | SCOR Simple Compact Reactor - An Innovative Medium-Sized PWR | 1 3 |
| 3227 | Cdrom | IRIS Pressurizer Design | 1 |
| 3201 | Cdrom | Integral Layout of the IRIS Reactor | 1 |
| 3129 | Cdrom | Status of Integrated Modular Water Reactor (IMR) Development | 1 |
Pierre Berbey, Electricité de France / SEPTEN; 12 avenue Dutrièvoz, ; Villeurbanne, 69628 &France; Ph: 33 47282 7135 FAX: 33 47282 7701 E-mail: pierre.berbey@edf.fr
| 3235 | Cdrom | Westinghouse AP1000 Advanced Passive Plant | 1 |
| 3028 | Cdrom | The EPR – A Safe and Competitive Solution for Future Energy Needs |
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
| 3294 | Cdrom | Research and Development Program of Innovative Simplified and Severe-Accident-Free BWR by High-Performance Steam Injector System | 1 6 |
| 3281 | Cdrom | Development of Medium Sized ABWR | 1 5 |
| 3008 | Cdrom | A Small Modular Advanced Reactor Technology (SMART) | 1 |
| 3275 | Cdrom | Development of Small Simplified Modular Reactor | 1 |
| 3317 | Cdrom | ALWR Spanish Industry Participation in Their Construction Phase | 1 3 |
Werner Brettschuh, Framatome ANP GmbH; NGPF, P.O. Box 101063 ; Offenbach, 63010 Germany; Ph: 0049 69 807 93527 FAX: 0049 69 807 94327 E-mail: Werner.Brettschuh@framatome-anp.com
| 3312 | Cdrom | Development of Next Generation BWR with Internal CRD | 6 1 |
| 3222 | Pres. | SWR 1000: Framatome ANP's Boiling Water Reactor | 1 |
| 3119 | Cdrom | ABWR-II Core Development: Economically Competitive 1700MWe BWR with Large Bundle Concept | 1 7 |
| 3003 | Pres. | ESBWR – Towards the New Era of Nuclear Reactors | 1 |
| 3353 | Pres. | Conceptual Core Catcher Design for Boiling Water Reactors | 1.04b |
Bob Twilley, Framatome; , ; , USA; Ph: FAX: E-mail: bob.twilley@framatome-anp.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
| 3188 | Cdrom | The Business Case for Building a New Nuclear Plant in the United States | 3 9 |
| 3009 | Cdrom | Co-generation Nuclear Power Plant with Innovative Simplified Passive Boiling Water Reactor VK-300 | 1 |
| 3043 | Cdrom | Regulatory Approach on Pool Temperature Limit of In-containment Refueling Water Storage Tank under Accident Condition | 1 |
| 3241 | Cdrom | Advances in CANDU NPP Technology and Construction Techniques | 1 |
| 3199 | Cdrom | A Report of the Latest Results of the Modularization: Technology in Nuclear Power Plant Construction |
| 3062 | Cdrom | Nuclear Power Plant Construction for Advanced Concepts | 1 2 |
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
| 3360 | Pres. | Invited Presentation | 1.09 |
| 3203 | Cdrom | Ability of Westinghouse AP1000 to Meet UK Licensing Requirements | 1 |
| 3271 | Cdrom | Using Immersive Virtual Environments to Develop and Visualize Construction Schedules for Advanced Nuclear Power Plants | 1.09 1.08 |
| 3153 | Cdrom | Development of the PRA for the AP1000 | 5 1 |
| 3316 | Cdrom | Spanish Contribution to the EPP/AP1000 Designs | 1 1 |
| 3361 | Cdrom | Assessment of the Potential for AP1000 Reactor Vessel Failure Induced by a Stratified Debris Bed with a Bottom Metal Layer during IVR | 1.09 |
Michael A. Fütterer, JRC Petten; P.O. Box 2, ; NL-1755 ZG Petten, The Netherlands; Ph: 31-224-565158 FAX: 31-224-565638 E-mail: fuetterer@jrc.nl
Nathalie Chauvin, CEA Cadarache; DEN/DEC/SESC, ; F-13108 St. Paul-lez-Durance, France; Ph: FAX: E-mail: nchauvin@cea.fr
| 3095 | Cdrom | HTR Fuel Cycles: a Comprehensive Outlook of Past Experience and an Analysis of Future Options |
| 3081 | Cdrom | HTR Kernel-by-Kernel Fuel Spherical Model Burnup Analysis | 2 7 |
| 3020 | Cdrom | First Results from HTR-F&F1 Projects: High Temperature Reactor Fuel Technology | 2 |
| 3017 | Cdrom | First Results from HTR-F Project : Modelling of Fission Products Diffusion in High Temperature Gas Reactors Fuel | 2 |
| 3344 | Final | European Programme on High Temperature Reactor Nuclear Physics, Waste and Fuel Cycle Studies |
| 3015 | Cdrom | First Results from HTR-E Project: High Temperature Components and Systems | 2 |
| 3260 | Cdrom | Comparative Design Study of Carbon Dioxide Gas Turbine and Helium Gas Turbine for HTGR Power Plant | 2 |
| 3213 | Cdrom | The Development of High Efficiency Heat Exchangers for Helium Gas Cooled Reactors | 2 |
| 3174 | Cdrom | Research & Development Programme on HTR Materials | 2 |
| 3094 | Cdrom | Thermal Conductivity of Graphite Irradiated With Medium and High Neutron Fluences |
| 3355 | Cdrom | High Temperature Reactor Pressure Vessel Materials | 2 |
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
| 3023 | Cdrom | Steady-State and Accident Analyses of HTR with the Computer Code CATHARE | 2 |
| 3102 | Cdrom | Experimental Investigation of Thermal Hydraulic Characteristics in Pebble Beds Placed Between Axially Streamlined Cylinders | 2 2 |
| 3239 | Cdrom | Large Eddy Simulation for High Temperature Gas Cooled Reactors | 2 6 |
| 3295 | Cdrom | Operational Control and Protection Systems of the Pebble Bed Micro Model (PBMM) Plant at the Potchefstroom University for CHE | 2 |
Michael A. Fütterer, JRC Petten; P.O. Box 2, ; NL-1755 ZG Petten, The Netherlands; Ph: 31-224-565158 FAX: 31-224-565638 E-mail: fuetterer@jrc.nl
| 3264 | Cdrom | Operation and Simulation of a Three-shaft, Closed Loop, Brayton Cycle Model of the PBMR Power Plant | 6 |
| 3292 | Cdrom | Thermal-Flow Comparison of Three- and Single Shaft Closed Loop Brayton Cycle Configurations for HTGR Power Conversion | 2 |
| 3313 | Cdrom | Zero Waste Heat Release Nuclear Cogeneration System | 9 2 |
| 3160 | Cdrom | A Quasi-Steady State Analysis of the CO2 Recompression Brayton Cycle | 2 |
| 3171 | Cdrom | The Production of Nuclear Hydrogen by Means of Process Heat from HTGRs | 2 |
Dan Serbanescu, PBMR; Gordon Hood Avenue 1267 POBox 9396, ; Centurion, Gauteng 46 South Africa; Ph: (27012) 677 9414 FAX: (27012) 677 9940 E-mail: serband@pbmr.co.za
| 3327 | Cdrom | Safety Approach and Licensing Issues for High Temperature Gas Cooled Reactors: First Results of the EC-funded HTR-L Project | 2.06 |
| 3234 | Cdrom | The Use of PRA During the Design Phase of the PBMR | 2 5 |
| 3233 | Cdrom | Risk, Entropy, Synergy and Uncertainty in the Calculations of Gas Cooled Reactors of PBMR Type | 2 5 |
Michael A. Fütterer, JRC Petten; P.O. Box 2, ; NL-1755 ZG Petten, The Netherlands; Ph: 31-224-565158 FAX: 31-224-565638 E-mail: fuetterer@jrc.nl
| 3180 | Cdrom | Nuclear Power Plant Concepts with Dynamic and Static Combined Energy Conversion | 2 4 |
| 3178 | Cdrom | ACACIA: A Small Scale Power Plant With Pebble Bed Cartridge Reactor | 2 |
| 3013 | Cdrom | Application of CANDLE Burnup to Block-Fuel High Temperature Gas Reactor | 2 6 |
Philippe Billot, CEA Saclay; DEN/DDIN, ; F-91191 Gif-sur-Yvette, France; Ph: FAX: E-mail: philippe.billot@cea.fr
| 3053 | Cdrom | Flexibility of the Gas Cooled Fast Reactor to Meet the Requirements of the 21st Century | 3 7 |
| 3167 | Cdrom | Gas-Cooled Fast Reactor Concept Review Studies (GCFR) |
| 3332 | Abs.a | A Core Design Study of Helium Cooled Fast Reactor with Coated Particle Fuel in Current Feasibility Study on Commercialized Fast Reactor Cycle System in Japan | 2 7 |
| 3106 | Cdrom | Preliminary Design of an Advanced Gas Cooled Fast Reactor Core, Fuel Forms and Primary System Concept |
Philippe Billot, CEA Saclay; DEN/DDIN, ; F-91191 Gif-sur-Yvette, France; Ph: FAX: E-mail: philippe.billot@cea.fr
| 3107 | Cdrom | Thermal-Hydraulic Design of a Gas Cooled Fast Reactor |
| 3105 | Cdrom | Core Transient Behaviour of the Gas Cooled Fast Reactor |
| 3211 | Cdrom | Thermal Hydraulics Analysis of a Plutonium-Burning Gas-Cooled Fast Reactor | 6 |
| 3339 | Cdrom | Requirements for Fuel and Structural Materials for Gas Cooled Fast Reactor (GFR), Preliminary Design |
Montserrat Casero, DTN; Glorieta de Quevedo, 9, 5ª planta, ; Madrid, 28015 Spain; Ph: 34 91 593 45 66 FAX: 34 91 593 49 37 E-mail: montserrat.casero@dtn.es
Jordi Roglans, Argonne Natl Lab; Reactor Analysis and Engineering Division, 9700 So. Cass Avenue ; Argonne , IL 60439 USA; Ph: 630-252-3283 FAX: 630-252-4620 E-mail: roglans@ra.anl.gov
Michael Lineberry, Argonne National Laboratory-West; , ; , USA; Ph: 208-533-7434 FAX: E-mail: Michael.lineberry@anl.gov
Moon Hee Chang, Korea Atomic Energy Research Institute(KAERI); P. O. Box 105, Yuseong, ; Daejeon, 305-600 Korea; Ph: 82-42-868-2818 FAX: 82-42-868-8990 E-mail: mhchang@kaeri.re.kr
Evelyne Bertel, OECD Nuclear Energy Agency; Nuclear Development Division, Le Seine St-Germain 12, boulevard des Iles; 92130 Issy-les-Moulineaux, France; Ph: 33-1-45 24 11 10 FAX: 33-1-45 24 10 65 E-mail: bertel@nea.fr
| 3110 | Cdrom | International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) |
| 3111 | Cdrom | User Requirements for Safety of Innovative Nuclear Reactors and Fuel Cycles |
| 3237 | Cdrom | Materials Needs for Generation IV Nuclear Energy Systems | 3 |
| 3204 | Cdrom | Virtual Reality: At the Service of GEN-IV, and V, and …. | 4 5 |
Poong Eil Juhn, International Atomic Energy Agency (IAEA); Division of Nuclear Power, Wagramer Strasse 5 P.O. Box 100; A-1400 Vienna, Austria; Ph: 43 1 2600/22814 FAX: 43 1 26007 E-mail: P.E.Juhn@iaea.org
Juergen KUPITZ, IAEA; , ; , ; Ph: FAX: E-mail: J.Kupitz@iaea.org
| 3091 | Cdrom | International Co-operation for the Development of Advanced Nuclear Energy Systems | 3 9 |
| 3136 | Cdrom | Some Aspects of Future Deployment of Nuclear Energy in the Czech Republic | 3 7 |
| 3176 | Cdrom | The International Science and Technology Center (ISTC) and ISTC Projects on Innovative Reactors and Fuel Cycle (Information Review) | 3 |
| 3144 | Cdrom | S-PRISM Fuel Cycle Study | 3 |
| 3169 | Cdrom | Some Aspects of Slow Nuclear Burning Reactor | 3 7 |
Todd Allen, Argonne National Laboratory-West; PO Box 2528, ; Idaho Falls, ID 83401-2528 USA; Ph: 208-533-7760 FAX: 208-533-7799 E-mail: Todd.allen@anlw.anl.gov
Jordi Roglans, Argonne Natl Lab; Reactor Analysis and Engineering Division, 9700 So. Cass Avenue ; Argonne , IL 60439 USA; Ph: 630-252-3283 FAX: 630-252-4620 E-mail: roglans@ra.anl.gov
| 3214 | Cdrom | Design of the Advanced Fast Reactor System | 3 9 |
| 3142 | Cdrom | S-PRISM High Burnup Metal-Fuel Core Design | 3 |
| 3012 | Cdrom | Advanced NPP’s on Modular Lead-Bismuth Cooled Fast Reactors | 3 9 |
| 3064 | Cdrom | Turbine Design for a Supercritical Carbon Dioxide Gas Turbine Brayton Cycle | 3 6 |
| 3115 | Cdrom | Updated Thermal Hydraulic Analyses for Recent ENHS Design Improvements | 3 6 |
| 3220 | Cdrom | Shielding Optimization of the ENHS Reactor |
Tom Lennox, NNC Limited; Booths Hall , Chelford Raod ; Knutsford, Cheshire , WA16 8QZ United Kingdom; Ph: 44 (0) 1565843470 FAX: 44 (0) 1565843878 E-mail: Tom.lennox@nnc.co.uk
| 3074 | Cdrom | The Analysis of Radiological Consequences Due to Hypothetical Core Disruptive Accident in KALIMER | 3 5 |
| 3208 | Cdrom | Inherent Safety of the KALIMER Breakeven Core Design for Various ATWS Events | 3 6 |
| 3145 | Cdrom | S-PRISM’s Advanced Steam Generator Leak Protection System | 3 |
| 3165 | Cdrom | A Reliable Steam Generator that Will Allow the Elimination of the Secondary Sodium Circuit in an LMFBR |
| 3262 | Cdrom | Computer Code QUARK-LP ver.4 for Simulation of Tube Rupture Propagation due to Overheating in LMFBR Steam Generator |
| 3103 | Cdrom | Innovative Sodium/Water Reaction Mitigation System for a Large Sized Steam Generator of Fast Breeder Reactor | 4 |
Ehud Greenspan, Univ of California-Berkeley; , ; , ; Ph: FAX: E-mail: gehud@nuc.berkeley.edu
| 3002 | Cdrom | Physical and Chemical Properties of Molten Salt Reactor Fuel Salts | 3 8 |
| 3030 | Cdrom | Reactor Physics & Fuel Cycle Analysis of a Molten Salt Advanced Reactor Transmuter | 3 3 |
| 3287 | Cdrom | Temperature Feedbacks of a Thermal Molten Salt Reactor: Compromise between Stability and Breeding Performances | 3 |
Yoshiaki Oka, University of Tokyo ; 1-19-6 Kohinata, Bunkyo-ku, ; , Tokyo 112-0006 Japan; Ph: 03-5841-7418 , 029-287-8440 (Tokai-mura) FAX: 03-5841-8632, 029-287-8439 (Tokai-mura) E-mail: oka@tokai.t.u-tokyo.ac.jp, oka@nucl.jp
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
| 3257 | Cdrom | Conceptual Design of High Temperature Reactors Cooled by Supercritical Light Water | 1 |
| 3258 | Cdrom | Progress of Development Project of Supercritical-water Cooled Power Reactor, 2003 | 3 1 |
| 3137 | Cdrom | Overview of the HPLWR Project and Future Direction | 3 1 |
| 3046 | Cdrom | Potential Plant Characteristics of a High Performance Light Water Reactor (HPLWR) | 3 |
| 3194 | Cdrom | Core Design Feature Studies and Research Needs for High Performance Light Water Reactors | 3 7 |
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
| 3044 | Cdrom | Validation of Coupled Neutron Physics and Thermal-hydraulic Analysis for HPLWR | 3 7 |
| 3146 | Cdrom | Preliminary Calculations of a Supercritical Light Water Reactor Concept Using the CATHARE Code | 3 6 |
| 3240 | Cdrom | Supercritical Boiling Water Reactor Concept with Micro-Fuel-Elements | 3 |
| 3223 | Cdrom | Thermal Hydraulic of Supercritical Pressure Water-Cooled Reactor Options | 1 |
| 3329 | Cdrom | Study of Solid Moderators for the Thermal-Spectrum Supercritical Water-Cooled Reactor (Thermo-Mechanics and Cost) | 3.08 |
| 3328 | Cdrom | Study of Solid Moderators for the Thermal-Spectrum Supercritical Water-Cooled Reactor (Neutronics) | 3.08 |
Jacques Balley, EDF Septen; , ; , France; Ph: 33 4 72827205 or 33 1 72827458 FAX: E-mail: jacques.balley@edf.fr
Claude Degrave, Electricite De France/SEPTEN; 12-14 Avenue Dutrievoz, ; 69628 VILLEURNANNE Cedex , France; Ph: 33-4-72-82-72-36 FAX: 33-4-72-82-77-01 E-mail: claude.degrave@edf.fr
Manuel Martín Ramos, SOLUZIONA; C/ Orense, 81. 3º, ; Madrid, 28020 Spain; Ph: (34) 91 384 71 00 FAX: (34) 91 571 14 16 E-mail: mmartinra@soluziona.com
Mikko Kosonen, Teollisuuden Voima Oy (TVO); , ; FIN-27160 Olkiluoto, Finland; Ph: 358-2-83-81-3210 FAX: 358-2-8381-3209 E-mail: Kosonen.Mikko@tvo.fi
William (Bill) Werner Strom, San Onofre Nuclear Generating Station; P.O. Box 128, 5000 Pacific Coast Hwy ; San Clemente , CA 92672 USA; Ph: 949-368-9785 FAX: 949-368-5360 E-mail: strombw@songs.sce.com
Sung Eun Tae, Korea Hydro & Nuclear Power Company (KHNP); , ; , Korea; Ph: FAX: E-mail: setae@khnp.co.kr
Man Gyun Na, Chosun University; Department of Nuclear Engineering, 375 Seosuk-dong, Dong-gu ; Kwangju, 501-759 Korea; Ph: 82-62-230-7168 FAX: 82-62-232-9218 E-mail: magyna@chosun.ac.kr
| 3255 | Cdrom | Estimation of the DNBR Distribution in a Hot Pin Using a Fuzzy Neural Network | 4 5 |
| 3254 | Cdrom | On-line Generation of Core Monitoring Three-dimensional Power Information with the Detector Signals and the Monitoring Constants Supplied by the Coupled Core Design Code | 4 5 |
| 3212 | Cdrom | An Estimation of the Effect of Helium-3 to the Tritium Generation in the CANDU PHWR | 4 5 |
| 3358 | Cdrom | Management and Automation of Set Point Calculations in NPP’S | 1 |
Claude Degrave, Electricite De France/SEPTEN; 12-14 Avenue Dutrievoz, ; 69628 VILLEURNANNE Cedex , France; Ph: 33-4-72-82-72-36 FAX: 33-4-72-82-77-01 E-mail: claude.degrave@edf.fr
| 3056 | Cdrom | Olkiluoto 1 and 2 - Optimized Annual Outages | 4 |
| 3224 | Cdrom | Volume Reduction of Nuclear Power Plant Process Waste | 4 3 |
| 3280 | Cdrom | Development of Coil Current Monitoring System for Control Element Drive Mechanism Control System | 4 5 |
| 3338 | Cdrom | Facing Information Management Solutions for SAT Applications: A Tecnatom´s Perspective | 4 |
Claude Degrave, Electricite De France/SEPTEN; 12-14 Avenue Dutrievoz, ; 69628 VILLEURNANNE Cedex , France; Ph: 33-4-72-82-72-36 FAX: 33-4-72-82-77-01 E-mail: claude.degrave@edf.fr
| 3259 | Cdrom | Optimization of the Photothermal Camera for Crack Detection | 4 |
| 3185 | Revd. | Preventive Maintenance of Pressure Sensors: Analysis of Pressure Signals Using a Singular System Analysis (SSA) Methodology | 4 |
| 3116 | Cdrom | The New BWR ID Tool AIRIS 21 for ISI and Its First Field Application in Japan | 4 5 |
| 3051 | Cdrom | Development of Yag Laser Repair Welding Robot for Underwater Environment | 4 |
Basma Shalaby, Atomic Energy of Canada Limited; 2251 Speakman Drive,, ; Mississauga, Ontario, L5K 1B2, Canada; Ph: (905) 823-9060 x2007 FAX: (905) 823-8821 E-mail: shalabyb@aecl.ca
| 3331 | Cdrom | RAM Guide Usable for NPP During Designing | 4 |
| 3288 | Cdrom | Methodology for Operability Calculations for Heat Exchangers Subject to Macrofouling | 4 |
| 3186 | Revd. | Simulation and Monitoring of a Nuclear Power Plant Condenser’s Thermal Performance | 4 |
| 3109 | Cdrom | Potential Benefits and Available Technologies for the Steam Cycle of a Next Generation Nuclear Plant | 4 |
| 3100 | Cdrom | Nuclear Power Plant I & C Design Verification by Simulation | 4 3 |
| 3356 | Cdrom | Main Ageing Issues to be Considered in the Design of New NPPs | 4 9 |
Philippe COPPE, EDF SEPTEN; 12 - 14, avenue Dutriévoz, ; VILLEURBANNE, 69003 France; Ph: 33 4 72 82 72 15 FAX: 33 4 72 82 77 01 E-mail: philippe.coppe@edf.fr
| 3283 | Cdrom | Analysis of Human Performance in KHNP NPPs | 4 5 |
| 3182 | Cdrom | Multi-objective Optimization of Testing and Maintenance Policies Based on Risk and Cost Criteria | 4 |
| 3242 | Cdrom | A Quantitative Assessment of Limiting Conditions for Operation Using a Concept of System Dynamics |
| 3337 | Cdrom | Human Factor Engineering Applied to Enhance the Nuclear Power Plant Design | 4 5 |
Sun-Koo Kang, KOPEC; 360-9, Mabuk-ri, Kusung-myon,Yongin-shi ; Kyunggido, 449-713 Korea; Ph: 82-31-283-6215 x01703 FAX: 82-31-284-4136 E-mail: skang@kopec.co.kr
| 3263 | Cdrom | Digital Reactor Protection System to Prevent Software Common Mode Failure | 4 |
| 3256 | Cdrom | Analysis of Hardware Reliabilities for NPP Digital I&C Equipment Predicted by Various Methods | 4 5 |
| 3097 | Cdrom | Reliability Assessment of Digital Protection Module in Korea Standard NPPs | 4 |
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
Carlos Padilla, DTN; , ; , Spain; Ph: 91 – 593.45.66 FAX: E-mail: carlos-m.padilla@dtn.es
Olli Kymäläinen, Fortum Nuclear Services; P.O. Box 10, ; Fortum, 00048 Finland; Ph: 358 10 453 5388 FAX: 358 10 459 5388 E-mail: Olli.Kymalainen@fortum.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
Carlos Padilla, DTN; , ; , Spain; Ph: 91 – 593.45.66 FAX: E-mail: carlos-m.padilla@dtn.es
| 3177 | Cdrom | Conversion of Cofrentes Nuclear Power Plant Model to the Consolidated Code TRAC-M and Comparative Analysis of a LOCA Performed with TRAC-BF1 and TRAC-M | 5 |
| 3128 | Cdrom | Effect of PLUS7 Debris Filtering Capability on the Long Term Cooling After a Loss of Coolant Accident | 5 6 |
| 3175 | Cdrom | Evaluation of Radiological Consequences of DBA and DEC Postulated Events Applied to the EP1000 Design | 5 |
| 3362 | Cdrom | Level-Swell Prediction with RETRAN-3D and its Application to a BWR Steam-Line-Break Analysis |
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
| 3215 | Cdrom | Analysis of a Pump Trip in a Typical Research Reactor by RELAP5/MOD3.3 | 5 6 |
| 3123 | Cdrom | Analysis of Heat Removal Transients by Secondary System for SMART | 5 |
| 3149 | Cdrom | Sensitivity Study on the Safety Parameters during ATWS with/without AMSAC | 5.13 |
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
| 3303 | Cdrom | Hydride Effects on Failure of High Burn-up LWR Fuel Rods under RIA Conditions | 5 7 |
| 3093 | Cdrom | Sensitivity Study on MDNBR Enhancement Methodologies in SMART Control Rod Bank Withdrawal Event | 5 |
| 3141 | Cdrom | Realistic and Conservative Rod Ejection Simulation in a PWR Core at HZP, EOC with Coupled PARCS and RELAP | 5 6 |
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
| 3217 | Cdrom | Safety Assessment of Advanced Nuclear Power Plants with the DSNP Modular Modeling System | 5 |
| 3155 | Cdrom | XADS Source Transients Analyzed by Means of RELAP5/PARCS | 5 6 |
| 3120 | Cdrom | Safety Analysis on Depressurization Accident of a Molten Salt Reactor | 5 4 |
| 3161 | Cdrom | Development of Regulatory Infrastructure for SMART-P Licensing | 1 3 |
Olli Kymäläinen, Fortum Nuclear Services; P.O. Box 10, ; Fortum, 00048 Finland; Ph: 358 10 453 5388 FAX: 358 10 459 5388 E-mail: Olli.Kymalainen@fortum.com
Jim Scobel, Westinghouse; Nuclear Services, 4350 Northern Pike ; Monroeville, PA 15146 USA; Ph: 412-374-5030 FAX: 412-374-5099 E-mail: scobeljh@westinghouse.com
| 3323 | Cdrom | Engineered Safety Features for In-Vessel Retention of Large Power Reactors | 5 5 |
| 3202 | Cdrom | On the Source Term Scrubbing within a Steam Generator under Dry Conditions of a SGTR Accident Sequence |
| 3078 | Cdrom | Addressing Design Extension Conditions in VVER-91/99 | 5 1 |
| 3067 | Cdrom | Experimental Study on In-Vessel Corium Retention through External Vessel Cooling Using Simulant Melt | 5 6 |
Sebastien Bachere, EDF; EDF SEPTEN, 12-14, avenue Dutrievoz ; Villeurbanne, 69100 France; Ph: (33) 4 72 82 73 06 FAX: (33) 4 72 82 77 14 E-mail: sebastien.bachere@edf.fr
| 3079 | Cdrom | Analysis of Long-term Loading of Containment under Severe Accidents | 5 6 |
| 3077 | Cdrom | Hydrogen Safety Concept of NPP with VVER-1000 Reactor | 5 6 |
| 3229 | Cdrom | APR1400 Containment System Design and Analysis | 5 6 |
| 3219 | Cdrom | An Evaluation of the Effectiveness of the APR1400 Hydrogen Mitigation System Using Sophisticated Lumped Parameter Code Coupled with 3-Dimensional Model | 5 6 |
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
| 3296 | Cdrom | Results and Insights from Probabilistic Safety Assessment for APR-1400 Standard Design | 1 |
| 3286 | Cdrom | Optimization of the Surveillance Test Interval of Integrated Leakage Rate Test at a PWR Plant in Taiwan | 5 4 |
| 3080 | Cdrom | Value-Impact Analysis of Risk-Informed Fire Analysis and Cable Tray Wrapping for a BWR-4 NPP in Taiwan | 1 5 |
| 3050 | Cdrom | On the Balanced Use between Formal Structured and Simplified Approaches for Reflecting Subjective Judgments of Experts | 5 5 |
| 3304 | Cdrom | The Evaluation of Dynamic Fault Tree Analysis to Maintenance Activities on a Simplified ECCS System | 5 1 |
| 3184 | Cdrom | Life Management of SSCs Using Plant Specific Indicators: Application to Heat Exchangers | 5 |
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
| 3197 | Cdrom | Study on Loss of Offsite Power in Safety Analysis |
| 3131 | Cdrom | Turbine/Generator Coastdown Test at YGN 5 | 5 5 |
| 3084 | Cdrom | Flow Field Analysis of Feeder Outlet Pipe in CANDU on Flow Accelerated Corrosion |
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
José L. Muñoz-Cobo, U.P.Valencia; , ; , Spain; Ph: 96-387.76.31 FAX: E-mail: jlcobos@iqn.upv.es
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
Jose Reyes, Oregon State University; 130 Radiation Center, ; Corvallis , OR 97331-5902 USA; Ph: 541-737-7065 FAX: E-mail: reyes@ne.orst.edu
Andre Gagnon, Westinghouse; Energy Center Site, 4350 Norther Pike ; Monroeville, PA 15146-2886 USA; Ph: 412-374-5574 FAX: 412-374-5139 E-mail: gagnonaf@westinghouse.com
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
Chin-Jang Chang , Institute of Nuclear Energy Research; Nuclear Engineering Division, P. O. Box 3-3 ; Lung-Tan , 325 TAIWAN; Ph: 886-2-23651717 ext. 6092 FAX: 886-3-4711404 E-mail: cjchang@iner.gov.tw
José L. Muñoz-Cobo, U.P.Valencia; , ; , Spain; Ph: 96-387.76.31 FAX: E-mail: jlcobos@iqn.upv.es
| 3040 | Cdrom | Investigations about Hydraulic Jump and Flooding Phenomena Concerning Hot Leg Injection in Pressurized Water Reactors | 6 |
| 3278 | Cdrom | Development of Particle Interaction Model of Large Bubbles in the Interfacial Area Transport Equation | 6 |
| 3104 | Cdrom | Experimental Investigation of Correlation Between Steam-water Flow Regime and Pressure Oscillation |
| 3122 | Cdrom | Critical Flow Calculation of Non-Condensable Gas, Water and Steam Mixture | 6 5 |
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
| 3289 | Cdrom | Experimental Study on the Effect of Axial Heat Flux on the CHF in Low-Flow Conditions With Vertical Annuli | 6 |
| 3333 | Cdrom | Augmentation of Critical Heat Flux Induced by Ultrasonic Wave on Inclined Surfaces | 6 |
| 3324 | Cdrom | One-Dimensional Downward-Facing Critical Heat Flux Concerning Surface Orientation and Gap Size Effects | 5 6 |
| 3322 | Cdrom | Film Boiling Heat Transfer from Downward-facing Hemispheres | 6 6 |
Francesco D’Auria, Università di Pisa; Dipartimento di Ingegneria, Meccanica, Nucleare e della Prodzione (DIMNP) Via Diotisalvi, 2; I-56126 Pisa, Italy; Ph: 39 050 836653 FAX: 39 050 836665 E-mail: dauria@ing.unipi.it
| 3173 | Cdrom | Fluent Simulation of Lighter-Than-Steam Noncondensable Gas Behavior in Vertical-Tube Heat Exchanger | 6 |
| 3118 | Cdrom | Numerical Analysis of an Axial Pump Performance Including Suction and Discharge for Integral Reactor SMART | 6 |
| 3251 | Cdrom | Numerical Investigations on In-Vessel Thermal Hydraulic Characteristics Related to Gas Entrainment Phenomena of Sodium-Cooled Fast Reactors | 6 |
| 3068 | Cdrom | The Comparison of Energetics between Sodium Vapor Explosion and Steam Explosion | 6 5 |
| 3319 | Cdrom | Thermal-Hydraulic Modelling of Heat Removal for the PBMR Helium Gas Cooled Reactor Using CFD | 6 2 |
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
| 3085 | Cdrom | Imaging of Two-Phase Flow in Rod Bundle with Dynamic Electrical Impedance Tomography | 6 |
| 3042 | Cdrom | Nonlinear Correlation Model for Estimation of Flow Profile Correction Factor of Ultrasonic Flow Meter in Nuclear Power Plants | 6 |
| 3007 | Cdrom | Numerical Prediction of Two-Phase Flow Induced Vibration in Pipe-Lines and Mitigation Methods | 6 |
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
| 3190 | Cdrom | Scaling and Parametric Studies of Condensation Oscillation in an In-containment Refueling Water Storage Tank | 6 4 |
| 3133 | Cdrom | Post-Test Analysis of Thermal-Hydraulic Test Using Full-Scale Horizontal PCCS Condenser | 6 |
| 3073 | Cdrom | UPTF Test 21D Counterpart Test in the MIDAS Test Facility under LBLOCA Late Reflood Phase | 6 5 |
| 3055 | Cdrom | Experimental Study on Gas Lift Pump Performance in Lead-Bismuth Eutectic | 6 |
| 3345 | Cdrom | Evaluation of the Reflooding Behavior of Blowdown and Condensation (B&C) Loop with a Prototypic Sparger Using the RELAP5 Code | 6 5 |
Andre Gagnon, Westinghouse; Energy Center Site, 4350 Norther Pike ; Monroeville, PA 15146-2886 USA; Ph: 412-374-5574 FAX: 412-374-5139 E-mail: gagnonaf@westinghouse.com
| 3004 | Cdrom | Overview of the New PANDA Test Results: Effects of Light Gases on Passive Safety Systems | 6 |
| 3049 | Cdrom | AP1000 Testing and Analysis Program at Oregon State University | 6 1 |
| 3326 | Cdrom | Scaling for the APR1400 Integral Test Facility | 6 |
| 3205 | Cdrom | Investigation of the Performance of IIST Passive Core Cooling System for Steam Generator Tube Rupture | 6 4 |
| 3193 | Cdrom | Experimental and Analytical Study on the Core Mixture Level Depletion after Safety Injection Failure during a Large-Break LOCA | 6 5 |
Francesco D’Auria, Università di Pisa; Dipartimento di Ingegneria, Meccanica, Nucleare e della Prodzione (DIMNP) Via Diotisalvi, 2; I-56126 Pisa, Italy; Ph: 39 050 836653 FAX: 39 050 836665 E-mail: dauria@ing.unipi.it
| 3019 | Cdrom | Evaluation of Adequacy of the VVER-1000 Natural Circulation Simulation at the PSB-VVER Test Facility | 6 6 |
| 3018 | Cdrom | Investigation of VVER-1000 Steam Line Break Accident in the PSB-VVER Test Facility | 6 |
| 3154 | Cdrom | Passive Heat Removal System for Reactor Plant of New Generation VVER-640. Design and Experimental Justification | 6 5 |
José L. Muñoz-Cobo, U.P.Valencia; , ; , Spain; Ph: 96-387.76.31 FAX: E-mail: jlcobos@iqn.upv.es
| 3198 | Cdrom | Coupled 3D Neutronic/Thermal-Hydraulic Codes Applied to PEACH Bottom Unit-2 | 6 |
| 3016 | Cdrom | Analysis of the PEACH Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS 3D Codes | 6 |
| 3334 | Draft | Study of the Unstable Behaviour in BWR Plant by Neutronic-Thermalhydraulic Coupling Codes |
| 3170 | Cdrom | Development of an Entrainment Model for the Steam Line Break Mass and Energy Release Analysis |
Francesco D’Auria, Università di Pisa; Dipartimento di Ingegneria, Meccanica, Nucleare e della Prodzione (DIMNP) Via Diotisalvi, 2; I-56126 Pisa, Italy; Ph: 39 050 836653 FAX: 39 050 836665 E-mail: dauria@ing.unipi.it
| 3298 | Cdrom | Flownet Nuclear Architecture, Implementation and Verification & Validation | 6 |
| 3151 | Cdrom | Lessons Learned from ISP-46 using RELAP/SCDAPSIM | 6 5 |
| 3352 | Cdrom | BAGIRA: A 3-D Thermal Hydraulic Code for Analysis of Complex Two-Phase Flow Phenomena | 6 |
Jose Reyes, Oregon State University; 130 Radiation Center, ; Corvallis , OR 97331-5902 USA; Ph: 541-737-7065 FAX: E-mail: reyes@ne.orst.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
| 3117 | Cdrom | A Computer Code Development for Blowdown Test Evaluation of Safety Injection Tank with a Fluidic Device | 6 4 |
| 3114 | Revd. | Development of a Computer Code for Thermohydraulic Analysis of a Heated Channel in Transients |
| 3247 | Cdrom | A Diffusion Nodal Green's Function Method for Cylindrical Geometry | 6 |
| 3143 | Cdrom | Peach Bottom Turbine Trip Analysis with TRAC/BF1-VALKIN | 6 7 |
| 3089 | Pres. | Validation of Containment Thermal Hydraulic Computer Codes for WWER Reactor | 6 5 |
Andre Gagnon, Westinghouse; Energy Center Site, 4350 Norther Pike ; Monroeville, PA 15146-2886 USA; Ph: 412-374-5574 FAX: 412-374-5139 E-mail: gagnonaf@westinghouse.com
| 3157 | Cdrom | Assessment of the Emergency Core Cooling System (ECCS) Performance for Advanced Plant Designs Using WCOBRA/TRAC | 6 5 |
| 3301 | Cdrom | Coupled RELAP5/GOTHIC Model for IRIS Reactor SBLOCA Analysis | 6 5 |
| 3300 | Cdrom | A Comprehensive Reactor Model for the Integrated Network Simulation of the PBMR Power Plant | 6 |
Chin-Jang Chang , Institute of Nuclear Energy Research; Nuclear Engineering Division, P. O. Box 3-3 ; Lung-Tan , 325 TAIWAN; Ph: 886-2-23651717 ext. 6092 FAX: 886-3-4711404 E-mail: cjchang@iner.gov.tw
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
| 3070 | Cdrom | An Experimental Study on the Two-Phase Natural Circulation through Annular Gap between Reactor Vessel and Insulation under External Vessel Cooling | 6 5 |
| 3243 | Cdrom | Realistic Analysis of Natural Circulation in Passive Nuclear Reactor Cooling System | 6 1 |
| 3207 | Cdrom | Experimental Investigation on Natural and Gas-injection Enhanced Circulation | 6 3 |
| 3307 | Cdrom | Evaluation of Natural Circulation Phenomena in WWER-1000 Geometry | 6 5 |
Isabel Gomez, Iberdrola Power Generation; Nuclear Fuel and Safety, Claudio Coello 53, 3º ; 28001 Madrid, Spain; Ph: 34 91 784 36 77 FAX: 34 91 784 31 78 E-mail: isabel.gomez@iberdrola.es
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
James Tulenko, University of Florida; Nuclear and Radiological Engineering, 202 NSC PO Box 118300; Gainesville, FL 32611-8300 USA; Ph: 352-392-1401 FAX: 352-392-3380 E-mail: tulenko@ufl.edu
Chan Oh Park, KEPCO Nuclear Fuel Co. (KNFC); , ; , Korea; Ph: FAX: E-mail: copark@mail.knfc.co.kr
Isabel Gomez, Iberdrola Power Generation; Nuclear Fuel and Safety, Claudio Coello 53, 3º ; 28001 Madrid, Spain; Ph: 34 91 784 36 77 FAX: 34 91 784 31 78 E-mail: isabel.gomez@iberdrola.es
| 3221 | Cdrom | On the Fueling of the Existing and Innovative Water Nuclear Reactors with a New Fuel Type-Total Safety | 7 1 |
| 3124 | Cdrom | Recycling Option of Thorium Fuel for PWR to Enhance the Fuel Economy | 7 7 |
| 3099 | Cdrom | RBMK-1500 Reactor Core Upgrading at Ignalina NPP. Uranium-Erbium Fuel and New Design Control Rods Implementation | 7 |
| 3025 | Cdrom | Production of Uranium-233 in ADS | 7 |
| 3024 | Cdrom | New Generation Elastic Neutron Absorber Systems to Address Nuclear Reactor Efficiency and Safety Issues | 4 4 |
James Tulenko, University of Florida; Nuclear and Radiological Engineering, 202 NSC PO Box 118300; Gainesville, FL 32611-8300 USA; Ph: 352-392-1401 FAX: 352-392-3380 E-mail: tulenko@ufl.edu
| 3232 | Cdrom | Benchmark on the 3-D VENUS-2 MOX Core Measurements | 7 |
| 3036 | Cdrom | The REBUS Experimental Programme for Burn-Up Credit | 7 |
| 3159 | Cdrom | A Burnup Credit Methodology for PWR Spent Fuel Storage Pools | 3 7 |
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
| 3092 | Cdrom | Reload Core Design with Thorium Fuel Assemblies for APR-1400 |
| 3191 | Cdrom | Core and Core-internal Design for Integrated Modular Water Reactor (IMR) (2) | 7 1 |
| 3248 | Cdrom | Alternative Design Options for the ENHS (Encapsulated Nuclear Heat Source) Reactor Core | 7 |
| 3330 | Abs.a | Advanced Metal Fuel Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle System in Japan | 7 3 |
Chan Oh Park, KEPCO Nuclear Fuel Co. (KNFC); , ; , Korea; Ph: FAX: E-mail: copark@mail.knfc.co.kr
H. K. Joo, KAERI; , ; , Korea; Ph: FAX: E-mail: hkjoo@nanum.kaeri.re.kr
| 3125 | Cdrom | Critical Experiments on Reduced-Moderation BWR: BARS - Reactivity Coefficients Measurements | 1 7 |
| 3269 | Cdrom | SCYCLE –Advanced Loading Pattern Optimization Code Using New Algorithm | 7? |
| 3270 | Cdrom | MCYCLE –Advanced Multi-Cycle Reloading Optimization Code Using New Method | 7? |
| 3359 | Cdrom | Power Upgrading Analysis for Tehran Research Reactor | 7 |
Arturo Buenaventura, Empresarios Agrupados; c/ Magallanes, 3, ; Madrid, 28015 Spain; Ph: 34 91 309 80 00 FAX: 34 91 591 26 25 E-mail: abp@empre.es
K. K. Panahi, GE Nuclear Energy; GE-NE, M/C 747, 175 Curtner Ave. ; San Jose , CA 95125 USA; Ph: 408-925-1334 FAX: 408-925-1490 E-mail: karim.panahi@gene.ge.com
Todd Allen, Argonne National Laboratory-West; PO Box 2528, ; Idaho Falls, ID 83401-2528 USA; Ph: 208-533-7760 FAX: 208-533-7799 E-mail: Todd.allen@anlw.anl.gov
Travis W. Knight, University of Florida; INSPI, PO 116502 ; Gainesville , FL 32611 USA; Ph: 352-392-1427 FAX: 352-392-8656 E-mail: knight@inspi.ufl.edu
Tae Eun Jin, Korea Power Engineering Company (KOPEC); Director, Structural Integrity & Materials Group 360-9 Mabuk-ri, Guseong-eup; Yongin, Gyeonggi-do, 449-713 Korea; Ph: 82-31-289-4282 FAX: 82-31-289-3189 E-mail: jinte@ns.kopec.co.kr
Derek Buckthorpe, NNC Ltd; Booths Hall, Chelford Road Knutsford; Cheshire , WA16 8QZ UK; Ph: 44 1565 84 3845 FAX: 44 1565 84 3878 E-mail: Derek.buckthorpe@nnc.co.uk
Arturo Buenaventura, Empresarios Agrupados; c/ Magallanes, 3, ; Madrid, 28015 Spain; Ph: 34 91 309 80 00 FAX: 34 91 591 26 25 E-mail: abp@empre.es
| 3284 | Pres. | Improving the Reliability of Valve Seat Material for a Nuclear Power Plant with Ultrasonic Testing | 8 |
| 3261 | Cdrom | Shape Optimization of a Flat Pressure Vessel Cover Having Elliptical Bottom Profile with Perforations |
| 3139 | Cdrom | Leak Before Break Procedure for High Temperature Applications - Improvement and Validation | 8 2 |
| 3006 | Cdrom | Mechanism of Vibration Excitation in the RBMK Fuel Assemblies | 8 7 |
| 3354 | Abs.a | An Overview of Proactive Management of Materials Degradation Issues in Modern Boiling Water Reactors | 8.01 |
Olivier DUGNE, CEA; DEN/DTE/STME/LMAC, BP 111 ; PIERRELATTE, 26702, France; Ph: 33475507570 FAX: 33475504768 E-mail: olivier.dugne@cea.fr
Travis W. Knight, University of Florida; INSPI, PO 116502 ; Gainesville , FL 32611 USA; Ph: 352-392-1427 FAX: 352-392-8656 E-mail: knight@inspi.ufl.edu
| 3293 | Final | Corrosion Resistance of the Candidate Materials for the Fuel Claddings of the Supercritical-water Cooled Power Reactor | 8 |
| 3250 | Cdrom | Development of Transportation and Storage Dry Metal Cask | 8 |
| 3075 | Cdrom | A Methodology to Evaluate Grid-to-Rod Fretting Wear in PWR Fuel | 8 6 |
| 3238 | Cdrom | Mechanical Analysis of a PWR Core Baffle with Consideration of Irradiation Induced Creep of Bolts | 8 5 |
K. K. Panahi, GE Nuclear Energy; GE-NE, M/C 747, 175 Curtner Ave. ; San Jose , CA 95125 USA; Ph: 408-925-1334 FAX: 408-925-1490 E-mail: karim.panahi@gene.ge.com
| 3266 | Cdrom | Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors | 8 4 |
| 3031 | Cdrom | Behaviour of C-Based Materials in Contact to Oxidising Gases |
| 3200 | Cdrom | Post-test Calculations of Medium Scaled Pressure Vessel Creep Failure Experiments |
| 3346 | Cdrom | AP1000 Reactor Internals Flow-Induced Vibration Program | 8 1 |
| 3363 | Cdrom | Non-Linear Flow-Induced Vibrations of Cylindrical Tubes |
Jose-Manuel Alonso, ENUSA; SANTIAGO RUSIÑOL 12, ; MADRID, Spain; Ph: 34-91-347.42.59 FAX: 34-913 474 215 E-mail: jap@enusa.es
K. K. Panahi, GE Nuclear Energy; GE-NE, M/C 747, 175 Curtner Ave. ; San Jose , CA 95125 USA; Ph: 408-925-1334 FAX: 408-925-1490 E-mail: karim.panahi@gene.ge.com
Shivakumar Sitaraman, GE Nuclear Energy; M/C 772, 175 Curtner Ave. ; San Jose , CA 95125-1088 USA; Ph: (408)925-2432 FAX: (408)925-6633 E-mail: shivakumar.sitaraman@gene.ge.com
| 3290 | Cdrom | Modeling of Fission Gas Release in the Periphery of High Burnup UO2 Fuel | 1 |
| 3164 | Cdrom | Dielectric Properties on Gamma Ray Irradiated Ethylene Propylene Rubber | 5 |
| 3163 | Cdrom | MP98, New Passive Control Rod System for a Full and Extended Reactivity Control on LWR |
| 3216 | Cdrom | Fuel Performance Modeling of Internally and Externally Cooled Annular PWR Fuel | 8 7 |
| 3135 | Cdrom | IRINA: A New Wide Range In-core Neutron Fluence Rate Monitoring System | 7 5 |
Todd Allen, Argonne National Laboratory-West; PO Box 2528, ; Idaho Falls, ID 83401-2528 USA; Ph: 208-533-7760 FAX: 208-533-7799 E-mail: Todd.allen@anlw.anl.gov
Heishichiro Takahashi, Hokkaido University; Director of Center for Advanced Research of Energy Tchnology, ; , Japan; Ph: 81-11-706-6767 FAX: 81-11-757-3537 E-mail: takahash@ufml.caret.hokudai.ac.jp
Tae Eun Jin, Korea Power Engineering Company (KOPEC); Director, Structural Integrity & Materials Group 360-9 Mabuk-ri, Guseong-eup; Yongin, Gyeonggi-do, 449-713 Korea; Ph: 82-31-289-4282 FAX: 82-31-289-3189 E-mail: jinte@ns.kopec.co.kr
| 3310 | Cdrom | Materials for High Performance Light Water Reactors | 8 1 |
| 3209 | Cdrom | Overview on the Materials Corrosion and Impurities Concentration in the CANDU Steam Generator | 8 |
| 3225 | Cdrom | Fracture Mechanics Analysis of Generic WWER-1000 RPV in PTS Event | 8 5 |
| 3063 | Cdrom | BWR Vessel and Internals Project Elements Applicable to Advanced Nuclear Power Plants | 8 |
| 3108 | Cdrom | Environmental Qualification of a New Generation Class 1E Special Cables for Yonggwang Nuclear Power Stations, Unit 5&6 in Korea |
| 3279 | Abs.a | High Performance SiC/SiC Composite R & D for Gas-Cooled Fast Reactor | 8 7 |
Ram Srinivasan, BNFL Fuel Solutions; 2105 S. Bascom Av, #160, ; Campbell, CA 95008 USA; Ph: (408)558-3510 FAX: (408)558-3518 E-mail: rsrinivasan@bnflinc.com
E. Altstadt, Forschungszentrum Rossendorf; Institute of Safety Research, P. O. Box 51 01 19 ; D – 01314 Dresden, Germany; Ph: 49 351 260 2276 FAX: 49 351 260 2002 E-mail: E.Altstadt@fz-rossendorf.de
| 3265 | Cdrom | In-Situ NDT Measurements of Irradiation-Induced Swelling in Core Internal Components | 8 4 |
| 3083 | Cdrom | The Effect of Bulk Composition on Radiation Damage in Austenitic Alloys | 8 |
| 3285 | Pres. | Irradiation and SCC Properties of Metals under Supercritical -water Cooled Power Reactor Conditions | 8 |
Gian-Luigi Fiorini, CEA; CEA/Saclay, DEN/DDIN bat 121 ; 91191 Gif sur Yvette Cedex , France; Ph: 33 1 69 08 63 95 FAX: 33 1 60 08 58 92 E-mail: gian-luigi.fiorini@cea.fr
Piluca Núñez, Spanish Nuclear Forum; Boix y Morer 6, 3ª planta ; 28003 Madrid, Spain; Ph: 34 91 553 63 03 FAX: 34 91 535 08 82 E-mail: piluca@foronuclear.org
Simon Nisan, CEA, DRN/DER/SERSI; CEN Cadarache, Bâtiment 212,, ; SAINT PAUL-LEZ-DURANCE , F-13108 France; Ph: (33) [0] 4 42 25 46 28 FAX: (33) [0] 4 42 25 40 46 E-mail: nisan@latour.cad.cea.fr
Lee Peddicord, Texas A&M University; , ; , USA; Ph: 979-458-6913 FAX: E-mail: k-peddicord@tamu.edu
David Wade, Argonne Natl Lab; , ; , USA; Ph: FAX: E-mail: dcwade@anl.gov
Piluca Núñez, Spanish Nuclear Forum; Boix y Morer 6, 3ª planta ; 28003 Madrid, Spain; Ph: 34 91 553 63 03 FAX: 34 91 535 08 82 E-mail: piluca@foronuclear.org
EUGENIO VIVES, Asociación Nuclear Ascó- Vandellos II; Aptdo Correos 48, L'hospitalet de l'infant 43890 Tarragona ; , Spain; Ph: 34977818853 FAX: 34977818889 E-mail: evives@anacnv.com
| 3305 | Cdrom | Toward A New Nuclear Regime | 3 9 |
| 3181 | Cdrom | Optimization of Electrical Supply Planning under Constraints of Environmental Impact and Economy | 9 |
| 3098 | Cdrom | The Global Nuclear Legacy and its Implication on The Sustainability of Nuclear Power | 9 |
| 3029 | Cdrom | Absent Atomic Power CO2 Doubles Before 2050 | 9 1 |
Piluca Núñez, Spanish Nuclear Forum; Boix y Morer 6, 3ª planta ; 28003 Madrid, Spain; Ph: 34 91 553 63 03 FAX: 34 91 535 08 82 E-mail: piluca@foronuclear.org
CLAUDIO VALLEJO, Union Fenosa Group; , ; , Spain; Ph: FAX: E-mail:
| 3166 | Cdrom | Virtual Reality: A Tool for the Procedures Optimization and Design of Advanced Nuclear Power Plants |
| 3082 | Cdrom | Repository Storage Strategy with Central Station Processing | 9 |
| 3179 | Cdrom | CAREM: Nuclear Safety Internalized Cost-Effectively from the Concept Genesis |
Simon Nisan, CEA, DRN/DER/SERSI; CEN Cadarache, Bâtiment 212,, ; SAINT PAUL-LEZ-DURANCE , F-13108 France; Ph: (33) [0] 4 42 25 46 28 FAX: (33) [0] 4 42 25 40 46 E-mail: nisan@latour.cad.cea.fr
| 3150 | Cdrom | Sustainable PWR Fuel Cycle with Complete TRU Recycling Using Fertile-Free Fuel | 3 7 |
| 3054 | Cdrom | A Study of Radiotoxicity Reduction Through Plutonium and Minor Actinide Recycling in Hypothetical Fuel Cycles using the Gas Cooled Fast Reactor | 3 9 |
| 3026 | Cdrom | Radiation Characteristics of Thorium Spent Fuel of Power Reactors at Long-Term Storage | 9 7 |
Tim J. Abram, BNFL; Springfields, ; PRESTON , PR4 0XJ United Kingdom; Ph: 44 1772 764696 FAX: 44 1772 762470 E-mail: tim.j.abram@bnfl.com
| 3314 | Cdrom | Concept of Spray Type Fast Reactor (STFR) Cooled by Light Water | 3 9 |
| 3277 | Cdrom | Nuclear Energy System with Reduced Moderation LWR and Advanced Recycle Systems | 9 1 |
| 3148 | Cdrom | A Proposed Idea for Hybrid and Electro-Nuclear Collapse Reactor |
| 3364 | Cdrom | Toward Optimum Utilization of Fission Power with Gaseous Fuel Reactors |
| 3347 | Cdrom | Fully Integrated Fuel Cycle and Actinide Burning with Gas Core Reactors | 9 |
| 3357 | Abs.a | European Project PDS XADS-- Accelerator Driven System (ADS) Engineering Activities | 3 |
Simon Nisan, CEA, DRN/DER/SERSI; CEN Cadarache, Bâtiment 212,, ; SAINT PAUL-LEZ-DURANCE , F-13108 France; Ph: (33) [0] 4 42 25 46 28 FAX: (33) [0] 4 42 25 40 46 E-mail: nisan@latour.cad.cea.fr
| 3039 | Cdrom | Simulation-Based Performance Analysis of a System for the Removal of Tritium from LHD Exhaust Gases | 3 9 |
| 3045 | Cdrom | Calculation of Deuteron Interactions within Microcracks of a D2 Loaded Crystalline Lattice at Room Temperature | 9 |
| 3101 | Cdrom | Uranium Resources: How Much Shall We Rely Upon Sea Water | 9 |
| 3022 | Cdrom | Site Specific Studies on Nuclear Desalination in the Mediterranean: the EURODESAL, TUNDESAL and AMANE Projects | 9 9 |
| 3132 | Cdrom | Long-term Perspective of Nuclear Energy Supply Using Uranium Extracted from Seawater | 8 3 |
| 3087 | Cdrom | Production of Excess Thermal Power from Non-equilibrium Nuclear Transmutation in a Solid Medium | 9 |
Melissa K. Van Dyke , NASA/MSFC; TD40, ; Huntsville, AL 35812 USA; Ph: 256-544-5720 FAX: 256-544-5926 E-mail: melissa.vandyke@msfc.nasa.gov
Arturo Buenaventura, Empresarios Agrupados; c/ Magallanes, 3, ; Madrid, 28015 Spain; Ph: 34 91 309 80 00 FAX: 34 91 591 26 25 E-mail: abp@empre.es
Norbert Frischauf, European Space & Technology Centre (ESA/ESTEC); 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
Michael G. Houts , NASA MSFC; TD40, ; MSFC , AL 35812 USA; Ph: 256-544-7143 FAX: 256-544-5926 E-mail: michael.houts@msfc.nasa.gov
Richard Heidmann, Planete mars; 28, rue de la gaite, ; 75014-Paris, France; Ph: 33(0)672958927 FAX: E-mail: RHeidmann@aol.com
Melissa K. Van Dyke , NASA/MSFC; TD40, ; Huntsville, AL 35812 USA; Ph: 256-544-5720 FAX: 256-544-5926 E-mail: melissa.vandyke@msfc.nasa.gov
| 3348 | Cdrom | Low Weight and Compact Space Power with Vapor Core Reactors | 10 |
| 3041 | Cdrom | Conceptual Design of Space Nuclear Power Plant with the SAFE-300 Type Reactor and Thermoelectric Energy Converters | 10 |
| 3340 | Cdrom | Mars Mission Concepts Incorporating a 3 kWe Surface Fission Power System | 10 |
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
| 3335 | Cdrom | Concept for a Shuttle-Tended Reusable Interplanetary Transport Vehicle Using Nuclear Electric Propulsion | 10 10 |
| 3196 | Cdrom | Development of Radioisotope Energy Conversion Systems - Efficient Radioisotopic Power | 10 |
| 3001 | Cdrom | Energy Conversion Options for NASA’s Space Nuclear Power Systems Initiative | 10 |
Norbert Frischauf, European Space & Technology Centre (ESA/ESTEC); 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
| 3350 | Cdrom | Square Lattice Honeycomb Tri-Carbide Fueled Reactor Design for Space Power and Propulsion | 10 |
| 3112 | Cdrom | Nuclear Thermal Propulsion – A Closer Look at the Physics, Various Technical Implementations and at Ongoing Activities Related to Research and Development | 10 |
| 3365 | Pres. | Project Am242 for Nuclear Space Engine |
Thomas Godfroy, NASA; , ; , USA; Ph: FAX: E-mail: Thomas.J.Godfroy@nasa.gov
| 3343 | Cdrom | Thermally Simulated Testing of a Direct-Drive Gas-Cooled Nuclear Reactor | 10 |
| 3342 | Cdrom | Early Flight Fission Test Facilities (EFF-TF) and Concepts That Support Near-Term Space Fission Missions | 10 |
| 3336 | Cdrom | Advanced Simulation Tools Applied to Systems of Nuclear Propulsion for Space Vehicles | 10 |
Melissa K. Van Dyke , NASA/MSFC; TD40, ; Huntsville, AL 35812 USA; Ph: 256-544-5720 FAX: 256-544-5926 E-mail: melissa.vandyke@msfc.nasa.gov
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