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| Home | Organizers | Call For Papers | Papers/Program | Highlights | Anaheim/Hotel | 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 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 11.00: Reactor Physics and Analysis |
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| 14.00: Plenary Sessions
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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
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
| 8338 | Cdrom | IRIS: A Comprehensive Approach to Nuclear Power in Smaller-Sized and Developing Countries | 10 1 |
| 8110 | Cdrom | Justification and Manufacturing Quality Assurance for the Use of Hot Isostatically Pressed, Reactor Coolant System Components in PWR Plant | 1 8 or 13 |
| 8249 | Cdrom | EPR: High Load Variation Performances with the Tmode Core Control | 1 4 |
| 8237 | Cdrom | An Integrated PWR for Marine Propulsion | 1 12 |
| 8031 | Cdrom | European Passive Plant (AP1000 -Europe) Design Status | 1 |
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
| 8411 | Cdrom | The Safety Concept of the SWR 1000 with Active and Passive Safety Systems | 1 |
| 8389 | Cdrom | SWR 1000: Efficient Design for Operational Excellence | 1 |
| 8345 | Cdrom | ESBWR Power Maneuvering via Feedwater Temperature Control | 1 4 |
| 8341 | Cdrom | Role of Human Factors in System Safety | 1 2 |
| 8228 | Cdrom | Coupled Regional Stability Analysis of Natural Circulation BWRs | 1 6 |
| 8054 | Cdrom | SWR 1000 Integral and Full Scale Tests of the Passive Safety Systems | 6 1 |
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
| 8410 | Cdrom | Optimization Planning for the Construction of the U.S. EPR | 1 4 |
| 8317 | Cdrom | Experimental Investigation of Non-condensable Gases Effect on Operation of VVER Steam Generator in Condensation Mode | 1 6 |
| 8091 | Cdrom | European Research on Issues Concerning Hydrogen Behaviour in Containment within the SARNET Network of Excellence | 1 |
| 8036 | Cdrom | Economic Advantage of the Korea Nuclear Plants by Shortening the Construction Schedule | 1 |
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
| 8216 | Cdrom | Study on High Conversion Type Core of Flexible Fuel Cycle (FLWR) for Minor Actinide (MA) Recycling | 1.02 |
| 8417 | Cdrom | A Review of Dopants Used to Increase UO2 Burnup Capabilities by Grain Size Modification | 8 |
| 8004 | Cdrom | A Comparative Evaluation of Pressurizer Surge Line Thermal Loads | 4 8 |
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
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
| 8433 | Cdrom | Why HTR/VHTR? A European Point of View | 2 9 |
| 8211 | Cdrom | Design, Analysis and Development for the Modular PB-AHTR | 2 3 |
| 8079 | Cdrom | Using Helicoids to Eliminate Hot Streaking and Stratification in the Very High Temperature Reactor Lower Plenum | 2 6 |
| 8103 | Cdrom | Risk Minimization for Near-Term Deployment of the Next Generation Nuclear Plant | 2 10 |
| 8104 | Cdrom | Neutronic Performance of High Molecular Weight Coolants for a Prismatic VHTR | 1 11 |
Kevan D. Weaver, Intellectual Ventures; , ; , USA; Ph: FAX: E-mail: kweaver@intven.com
| 8175 | Cdrom | Gas Cooled Fast Reactor 2400 MWth, End of the Preliminary Viability Phase | 2 3 |
| 8289 | Cdrom | Studies of Unprotected Transients and Alternative Decay Heat Removal System for the Gas Cooled Fast Reactor (GFR) | 2 3 |
| 8184 | Cdrom | Preliminary Safety Analysis of the 2400 MWth Gas-cooled Fast Reactor | 2 5 |
| 8253 | Cdrom | Power Conversion System (PCS) Evaluation for the Next Generation Nuclear Plant (NGNP) | 2 10 |
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
| 8093 | Cdrom | Means, Methods and Performances of the AREVAs HTR Compact Controls | 2 8 |
| 8097 | Cdrom | Developments and Economical Aspects in the Fabrication of HTR Fuel Elements | 2. 03 7 |
| 8147 | Cdrom | Development of a Fission Product Release Analysis Code COPA-FPREL | 2.06 |
| 8241 | Cdrom | Review of Material Properties of Pyrolytic Carbon Coating Layers in Relation with QC Measurement in HTR Coated Particle Fuels | 2 |
| 8008 | Cdrom | Alloy 617 for the High Temperature Diffusion-Bonded Compact Heat Exchangers | 2 8 |
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
| 8134 | Cdrom | An Optimal Loading Principle of Burnable Poisons for an OTTO Refueling Scheme in Pebble Bed HTGR Cores | 2 |
| 8233 | Cdrom | Out-of-Core Fuel Cycle Characteristics of VHTRs with No On-Site Refueling | 2 7 |
| 8021 | Cdrom | Deployment of FBR/VHTR Systems for Japan's Future Energy Demands | 2 3 |
Patrick Dumaz, CEA; , ; , France; Ph: FAX: E-mail: patrick.dumaz@cea.fr
| 8023 | Cdrom | Implications of Air Ingress Induced by Density-Difference Driven Stratified Flow | 2.06 |
| 8128 | Cdrom | A Three-Dimensional Heat Transfer Analysis on the Prismatic Fuel Elements in the Very High Temperature Reactor | 2.6 6.7 |
| 8177 | Cdrom | 3D Thermal Simulation of Decay Heat Removal in a HTR Half Geometry | 2 |
| 8180 | Cdrom | TINTE Transient Results for the OECD PBMR 400 MW PBMR Benchmark | 2 11 |
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
| 8072 | Cdrom | Alternative Working Fluids to Reduce the Size of Turbomachinery in VHTR Plants | 2 2 |
| 8277 | Cdrom | Thermo-Economic Performance of HTGR Brayton Power Cycles | 2 |
| 8382 | Cdrom | Thermo-Chemical Behavior of a Laboratory Scale SO3 Decomposer | 2.07 6.09 |
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
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
| 8401 | Cdrom | Sodium Fast Reactors (SFRs) and Recyclers | 3.01 |
| 8378 | Cdrom | Near-term Deployment of the PRISM Sodium-cooled Fast Reactor | 3 7 |
| 8397 | Cdrom | Approach for FBR Commercialization in Japan | 3.01 |
| 8402 | Cdrom | An Innovative Design Approach to a Cost Effective Commercial Liquid Metal Reactor | 3.01 |
| 8404 | Abs.a | French Sodium Fast Reactor Program | 3.01 |
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
| 8415 | Abs.a | Aqueous Processing Technologies for the Treatment of Spent Nuclear Fuel | 3.02 |
| 8413 | Abs.a | The Electrochemical Fuel Cycle for Treatment of Fast Reactor Fuel | 3.02 3.01 |
| 8407 | Abs.a | Pyroprocessing Technologies for the Treatment of LWR Spent Fuel | 3.02 |
| 8398 | Abs.a | French-Japan Fuel Cycle and SFR Development Program in the Context of GNEP | 3 |
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
| 8158 | Cdrom | Design Approaches from Breakeven Core to TRU Burner Core Based on KALIMER-600 Reactor | 3 02 |
| 8074 | Cdrom | Conceptual Core Designs for a 1200MWe Sodium Cooled Fast Reactor | 3 11 |
| 8071 | Cdrom | Improving SFR Economics through Innovations from Thermal Design and Analysis Aspects | 3 6 |
| 8070 | Cdrom | RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors | 3 6 |
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
| 8150 | Cdrom | Design Studies of Large-Scale Sodium-Cooled TRU Burner | 3 2 |
| 8157 | Cdrom | Inherent Safety Evaluation of Pool-type Liquid Metal Fast Reactors by a Multidimensional Thermal-hydraulic Calculation | 3 6 |
| 8379 | Cdrom | Global Cooperation and Conceptual Design ARR and Recycling Strategy | 3 7 |
| 8374 | Cdrom | An Assessment of Annular Fuel for Sodium-Cooled Fast Reactors | 3 7 |
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
| 8226 | Cdrom | Development of Advanced Loop-Type Fast Reactor in Japan (1): Current Status of JSFR Development | 3-SFR-Japan |
| 8231 | Cdrom | Development of Advanced Loop-Type Fast Reactor in Japan (2): Technological Feasibility of Two-Loop Cooling System in JSFR | 3-SFR-Japan 12 |
| 8227 | Cdrom | Development of Advanced Loop-Type Fast Reactor in Japan (3): Easy Inspection and High Reliable Reactor Structure in JSFR | 3-SFR-Japan |
| 8223 | Cdrom | 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 |
| 8224 | Cdrom | Development of Advanced Loop-Type Fast Reactor in Japan (5): Adoption of Self-Actuated Shutdown System to JSFR | 3-SFR-Japan |
| 8082 | Cdrom | Development of Advanced Loop-Type Fast Reactor in Japan (6) Minor Actinide Containing Oxide Fuel Core Design Study for the JSFR | 3-SFR-Japan |
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
| 8136 | Cdrom | Studies on French SFR Advanced Core Designs | 3-SFR-French 11 |
| 8107 | Cdrom | Innovative Steam Generator Concepts for Sodium Fast Reactors | 3-SFR-French |
| 8096 | Cdrom | Sodium Fast Reactor Concepts | 3-SFR-French |
| 8037 | Cdrom | The Use of Gas Based Energy Conversion Cycles for Sodium Fast Reactors | 3-SFR-French |
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
| 8073 | Cdrom | Scoping Investigation into Viability of a Lead-Cooled Fast Reactor Demonstration Test Reactor (Demo) | 3 12 |
| 8115 | Cdrom | A Design and Safety Features of Small CANDLE Fast Reactor | 3 11 |
| 8149 | Cdrom | Nuclear Safety Evaluation of a LBE Cooled Transmutation Reactor, PEACER-300 | 3 11 |
| 8311 | Cdrom | Development of Transportable Capsule Version of PEACER Design | 3.04 |
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
| 8331 | Cdrom | Design and Analysis of 900 MWt Lead-Cooled Fast Reactor | 3 11 |
| 8309 | Cdrom | A 2400 MWth Liquid Lead-Cooled Flexible Conversion Ratio (FCR) Reactor | 3 |
| 8218 | Cdrom | Corrosion Test of Cr- and Al-containing Alloys in Static LBE at 550 C | 3 8 |
| 8029 | Cdrom | Comparison of the Hydraulics in Concentric and Three Feeder XT-ADS Windowless Spallation Target Designs | 3 6 |
| 8003 | Cdrom | Application of a Controlled Swirl in the XT-ADS Spallation Target | 3 6 |
X. Cheng, IKET/FZK; , ; , Germany; Ph: FAX: E-mail: Xu.Cheng@iket.fzk.de
| 8247 | Cdrom | Progress within the European Project High Performance Light Water Reactor Phase 2 (HPLWR Phase 2) | 3 |
| 8100 | Cdrom | Coolant Mixing in the Plenum of the HPLWR Three Pass Core | 3 1 |
| 8053 | Cdrom | Determination of Mixing Coefficients in a Wire-Wrapped HPLWR Fuel Assembly using CFD | 3 1 |
| 8339 | Cdrom | Numerical Simulation of a HPLWR Fuel Assembly Flow with Wrapped Wire Spacers | 3. 6. |
Joerg Starflinger, FZK; Forschungszentrum Karlsruhe GmbH, IKET, Bldg. 420 Hermann-von-Helmholtz-Platz 1; , ; Ph: FAX: E-mail: joerg.starflinger@iket.fzk.de
| 8050 | Cdrom | Thermo-Mechanical Stress and Deformation Analysis of a HPLWR Pressure Vessel and Steam Plenum | 3 1 |
| 8076 | Cdrom | Coupling Analysis on a New SCWR Core Design | 3 |
| 8078 | Cdrom | Prediction of Overheated Zones along the Wall of Strongly Heated Quasi-Fully Developed Pipe Flow at Supercritical Pressure | 3 1 |
| 8336 | Cdrom | Summary for Three Different Validation Cases of Water Coolant Flow in Supercritical Water Test Sections with the Code ANSYS CFX 11.0 | 3. 6. |
Charles Forsberg, MIT; Room 24-207A, 77 Massachusetts Avenue ; Cambridge, MA 02139 USA; Ph: (617)324-4010 FAX: E-mail: cforsber@mit.edu
| 8315 | Cdrom | Reactor Physical Program in the Frame of the MSR-SPHINX Transmuter Concept Development | 3 12 |
| 8026 | Cdrom | Design Options for the Advanced High-Temperature Reactor | 3 2 |
| 8108 | Cdrom | Use of a Liquid Salt Nuclear Reactor to Transmute Minor Actinides | 3 7 |
| 8025 | Cdrom | Designing the Advanced High-Temperature Reactor for Low Radionuclide Releases in a Beyond-Design-Basis Accidents | 3 2 |
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
| 8266 | Cdrom | Initial Status and Test Results from a Supercritical CO2 Brayton Cycle Test Loop | 2 3 |
| 8131 | Cdrom | Design of Small Centrifugal Compressor Test Model for a Supercritical CO2 Compressor in the Fast Reactor Power Plant | 3 12 |
| 8257 | Cdrom | Dynamic Modeling of the S-CO2 Recompression Cycle | 2 6 |
| 8203 | Cdrom | Controllability of the Supercritical Carbon Dioxide Brayton Cycle near the Critical Point | 3 12 |
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
| 8347 | Cdrom | Supercritical CO2 Brayton Cycle Compression and Control Near the Critical Point | 6 2 |
| 8372 | Cdrom | Comparative Analysis of Supercritical CO2 Power Conversion System Control Schemes | 6 3 |
| 8169 | Cdrom | Preliminary Design of a Turbomachinery for the Supercritical Carbon Dioxide Brayton Cycle Coupled to the KALIMER-600 | 3 6 |
| 8343 | Cdrom | Dynamic System Analysis of a Supercritical CO2 Compression Loop | 6 3 |
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
Edward Quinn, GE-Hitachi Nuclear Energy; , ; , USA; Ph: (910) 602-1768 FAX: E-mail: edward.quinn@ge.com
| 8418 | Cdrom | 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 |
| 8400 | Cdrom | A Novel Approach to Modeling Single Event Upsets in Digital Microelectronic Devices | 4.01 |
| 8395 | Cdrom | Licensing of Simple Digital Devices | 4.01 |
| 8327 | Cdrom | Switching Scheme of Data Communication Network for Safety System in Nuclear Power Plant | 4 |
| 8296 | Cdrom | An Advanced Plant Protection System for the Shin-Kori 3&4 Nuclear Power Plant | 4 |
Edward Quinn, GE-Hitachi Nuclear Energy; , ; , USA; Ph: (910) 602-1768 FAX: E-mail: edward.quinn@ge.com
| 8287 | Cdrom | Top-Mounted Incore Instrumentation Insertion Test for Westinghouse AP1000 | 4 8 |
| 8271 | Cdrom | Design of a Software Training System for Severe Accident Mitigation of Korean Standard Nuclear Power Plants | 4 5 |
| 8148 | Cdrom | APR1400 I&C Architecture with the Advanced Design Feature Including High Reliability and Maintainability | 4 5 |
| 8135 | Cdrom | Strategy for Establishing Integrated I&C Reliability of Operating Nuclear Power Plants in Korea | 4 5 |
| 8016 | Cdrom | Westinghouse AP1000 Protection & Safety Monitoring System | 4.01 1 |
Seth A. Swamy, Westinghouse; , ; , USA; Ph: FAX: E-mail: swamysa@westinghouse.com
| 8416 | Cdrom | SG Asset Management Model Application | 4 4 |
| 8313 | Cdrom | An Experience in Low Temperature Stress Corrosion Cracking at Steam Generator Coldleg Drain Nozzle for YGN 3 Unit | 4 8 |
| 8005 | Cdrom | Fatigue Crack Growth Impact on Leak-Before-Break Due to Mechanical Stress Improvement Process | 4 8 |
| 8001 | Cdrom | Effect of Structural Weld Overlay on Recommended Leak-Before-Break Margins | 4 8 |
Ken Ferguson, Ivara; 5046 Mainway, ; Burlington , Ontario, L7L 5Z1 Canada; Ph: (803) 642-0273 FAX: E-mail: fergkl@earthlink.net
| 8386 | Cdrom | Technology Success: Integration of Power Plant Reliability and Effective Maintenance | 4 |
| 8304 | Cdrom | Reliability Database Development and Plant Performance Improvement Effort at Korea Hydro & Nuclear Power Co. | 4 5 |
| 8164 | Cdrom | Risk-Informed Assessment of the Scope and Frequency of Technical Service and Repair at the Kozloduy Nuclear Power Plant | 4 5 |
Ken Ferguson, Ivara; 5046 Mainway, ; Burlington , Ontario, L7L 5Z1 Canada; Ph: (803) 642-0273 FAX: E-mail: fergkl@earthlink.net
| 8168 | Cdrom | Risk-Informed Assessment of the Scope and Frequency of Testing at the Kozloduy Nuclear Power Plant | 4 5 |
| 8042 | Cdrom | Application of Systems Engineering to Nuclear Power Plant Design | 4 13 |
| 8015 | Cdrom | Passing of Reactors WWER-1000 of NPP Kozloduy Bulgaria to Extended Fuel Cycle Operation (Implementation of 235U Higher Enriched Fuel) | 4 1 |
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, EDF; , ; , France; Ph: 33 4 72 82 72 07 FAX: E-mail:christian.clement@edf.fr
Nam Dinh, Royal Institute of Technology in Stockholm; , ; , Sweden; Ph: 46 8 790 9255 FAX: E-mail:nam.dinh@energy.kth.se
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
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
| 8376 | Cdrom | Assessment of Core Cooling Capability of Emergency Core Cooling System in LBLOCA Condition for TAPS#3&4 | 5 |
| 8258 | Cdrom | Large Break LOCA Analysis for TAPS-3&4 Using RELAP-5/MOD 3.2 | 5 |
| 8251 | Cdrom | Large Break Loss of Coolant Accident Analysis of VVER-1000 Reactor Using CATHARE Code | 5. 6. |
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
| 8260 | Cdrom | Assessment on the Integrity of Component Cooling Water System during DBA with LOOP for Kori 3,4 Unit | 5 5 |
| 8195 | Cdrom | Improvement of the Interfacial Drag Model in TRAC-PF1/IBER to Simulate Downcomer Boiling Phenomena | 5 |
| 8051 | Cdrom | Sensitivity Studies on Uncertainty Parameters and Code Modeling during LBLOCA | 5 6 |
| 8314 | Cdrom | Evaluation of Radiological Effects of the Injection of Argon Gases into Reactor Coolant System | 7 9 |
Eric Williams, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2779 FAX: E-mail: Eric.Williams@areva.com
| 8383 | Cdrom | Dynamic Structural Analysis Concerning Integrity Assessment of a Reinforced Concrete Ceiling due to Impact Loads | 9 |
| 8295 | Cdrom | Effect of Break Size on Severe Core Damage Behavior for VVER1000 Reactor with the ASTEC V1 Code | 5 |
| 8200 | Cdrom | MAAP4.0.7 Analysis for PRA Level 1 Mission Success Criteria | 5 6 |
| 8201 | Cdrom | MAAP4.0.7 Severe Accident Source Term Analysis | 5 6 |
| 8064 | Cdrom | Analysis of Station Blackout in the Gsgen Nuclear Plant | 5 6 |
| 8063 | Cdrom | SCDAP/RELAP5 Investigation on Coolability of Severely Degraded CANDU 6 Core Preliminary Results | 5 6 |
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
| 8198 | Cdrom | Relevant Scenarios and Uncertainty Analysis of Severe Accidents in the U.S. EPR | 5 6 |
| 8197 | Cdrom | Recent Revisions to MAAP4 for U.S. EPR Severe Accident Applications | 5 6 |
| 8183 | Cdrom | AREVA NP's Severe Accident Safety Issue Resolution Methodology for the U.S. EPR | 5 6 |
| 8006 | Cdrom | Influence of Jet Breakup Modeling on Ex-Vessel Steam Explosion Simulation Results | 5 6 |
Robert P. Martin, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2319 FAX: E-mail: robertp.martin@areva.com
| 8409 | Cdrom | Modeling of Two-Phase Natural Circulation in a Water Pool with Decay-Heated Debris Bed | 5 6 |
| 8328 | Cdrom | Thermodynamic Analysis for the Melt Pool Configuration during the Severe Accidents in the APR1400 | 5 6 |
| 8140 | Cdrom | Transient Conduction Heat Transfer Modelling in Concrete for the Simulation of Long Term Phase of Molten Core Concrete Interaction | 5 |
| 8052 | Cdrom | Interaction between Molten Corium UO2+x - ZrO2- FeOy and VVER Vessel Steel | 5 1 or 8 |
| 8047 | Cdrom | European Research on the Corium Issues within the SARNET Network of Excellence | 5 1 |
Markus Nie, AREVA NP; , ; , Germany; Ph: FAX: E-mail: markus.nie@areva.com
| 8065 | Cdrom | Pre-Test Calculational Support for the QUENCH-13 Experiment | 5 6 |
| 8390 | Cdrom | An Experimental Study on Debris Formation with Corium Simulant Materials | 5 1 |
| 8123 | Cdrom | An Investigation on the Material Effect on the Result of Fuel Coolant Interaction in the TROI Experiments | 5 |
| 8069 | Cdrom | Comparison of the High Temperature Steam Oxidation Kinetics of Advanced Cladding Materials | 5 8 |
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
| 8141 | Cdrom | Towards a Comprehensive Interpretation of 2D MCCI Tests | 5 |
| 8281 | Cdrom | Measurements of the Mechanical Strength of Corium Crusts | 5 |
| 8059 | Cdrom | Differences between Silica and Limestone Concretes that may Affect their Interaction with Corium | 5 8 |
| 8058 | Cdrom | Current European Experiments on 2D Molten Core Concrete Interactions: HECLA and VULCANO | 5 |
| 8098 | Cdrom | Interpretation of Real Material 2D MCCI Experiments in Homogeneous Oxidic Pool with the ASTEC/MEDICIS Code | 1 5 |
Karen Vierow, Texas A&M University; , ; College Station, TX USA; Ph: 979-458-0600 FAX: E-mail: vierow@ne.tamu.edu
| 8308 | Cdrom | Application of the ASTEC V1 Code to the LIVE-L1 Experiment | 5 6 |
| 8116 | Cdrom | Experimental and Post-Test Calculation Results of the Integral Reflood Test QUENCH-12 with a VVER-Type Bundle | Track 5: |
| 8086 | Cdrom | Direct Containment Heating Experiments for Konvoi Power Plants | 5 |
| 8032 | Cdrom | Triggered Steam Explosions with Corium Melts of Various Compositions in a Narrow Interaction Vessel in the TROI Facility | 5 |
Christian Clment, EDF; , ; , France; Ph: 33 4 72 82 72 07 FAX: E-mail: christian.clement@edf.fr
Takeshi Morita, JAPC; , ; , Japan; Ph: FAX: E-mail: takeshi-morita@japc.co.jp
| 8351 | Cdrom | A Study on the Operator's Communication Pattern Characteristics under Abnormal Operating Situation of Nuclear Power Plants | 5.05 |
| 8176 | Cdrom | Mechanism-based Ageing Management of Primary Water Stress Corrosion Cracking of Ni-base Components in PWR Environments | 5 8 |
| 8114 | Cdrom | A Study on the Verification and Validation of Programmable Logic Component in A Nuclear Power Plant | 5 4 |
| 8055 | Cdrom | U.S. NRCs Generic Issues Program | 13 5 |
Christian Clment, EDF; , ; , France; Ph: 33 4 72 82 72 07 FAX: E-mail: christian.clement@edf.fr
Takeshi Morita, JAPC; , ; , Japan; Ph: FAX: E-mail: takeshi-morita@japc.co.jp
| 8085 | Cdrom | Korean Experience in Periodic Safety Reviews and Safety Improvements of Operating Nuclear Power Plants | 5 |
| 8080 | Cdrom | Introduction of Regulatory Guide on Cyber Security of I&C Systems in Nuclear Facilities | 5 13 |
| 8035 | Cdrom | Resolution of Digital Instrumentation and Control and Human Factors Technical and Regulatory Issues for New Plants and for Modernization of Operating Plants | 5 13 |
Amy Slaga, AREVA NP; 3315 Old Forest Road, ; Lynchburg, VA 24506 USA; Ph: 434-832-2556 FAX: E-mail: amy.slaga@areva.com
| 8342 | Cdrom | Treatment of Complementary Events in Event Trees in Constructing Linked Fault Trees for Level 1 and Level 2 PRA | 5 |
| 8301 | Cdrom | Spatial Interactions Database Development for Effective Probabilistic Risk Assessment | 5 4 |
| 8259 | Cdrom | SIMPROC: Procedures Simulator for Operator Actions in NPPs | 5 6 |
| 8156 | Cdrom | A Study on Uncertainties Evaluation in Containment Event Tree | 5 |
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
| 8370 | Cdrom | The Comparison of Frequency-Consequence (F-C) Criteria in Evaluating the Risk of New or Existing Reactor | 2 5 |
| 8022 | Cdrom | Overview of the Activities of the OECD/NEA/NSC Working Party on Nuclear Criticality Safety | 13 5 |
| 8279 | Cdrom | Drafting and Implementation of a Practical Elimination Approach for Gen IV Nuclear Reactors | 5 |
| 8273 | Cdrom | EFIT Reactor Simulation Coupling Neutronics/Thermal-hydraulics with the RELAP5/PARCS Code | 7 5 |
| 8061 | Cdrom | Comparative Review of Design and Improved Safety Features of New LWR Plants | 5 |
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
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
| 8248 | Cdrom | Verification and Validation of Almaraz NPP TRACE Model | 6 1 |
| 8235 | Cdrom | Parametric Sensitivity Study on the Reflooding Models of the MARS Code Based on 6x6 Rod Bundle Test Results | 6 5 |
| 8117 | Cdrom | Implementation of a New Controlling Function in MELCOR Computer Code for Uncertainty Evaluations | 6 4 |
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
| 8394 | Cdrom | TRACG Statistical Method for BWR Loss-of-Coolant Accident Analyses | 6 5 |
| 8387 | Cdrom | BFBT Benchmark Sub-Channel Analysis with RELAP5-3D Code | 6 1 |
| 8375 | Cdrom | Assessment of Compensating Error in the WCOBRA/TRAC-TF2 Thermal-Hydraulic Code | 6 6 |
| 8269 | Cdrom | Development and Qualification of the Coupled Code System COBRA-TF/THREEDANT for the Pin-by-Pin Power Calculation | 11 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
| 8369 | Cdrom | An Improved Horizontal Flow Regime Map for the 1-D Module of WCOBRA/TRAC-TF2 | 6 6 |
| 8272 | Cdrom | Full-size and Scaled 3-loop Reactor Vessel Simulation for Boron Dilution Studies Using CFD | 6 |
| 8189 | Cdrom | MELCOR Validation against a PUMA Facility Main Steam Line Break Integral Test | 6 5 |
| 8129 | Cdrom | An Integral Effect Test on the Reflood Period of a Large-Break LOCA for APR1400 Using the ATLAS | 6 1 |
Shripad Revankar, Purdue Univ; , ; , USA; Ph: FAX: E-mail: shripad@purdue.edu
| 8124 | Cdrom | Experimental Validation of a Core Heat Transfer Model in the TASS/SMR Code Using Film Boiling Data | 6 1 |
| 8119 | Cdrom | PC-based Simulator PCTRAN for Advanced Nuclear Power Plants | 6 11 |
| 8106 | Cdrom | Analysis of Dynamic Behavior of MEGAPIE Cooling System | 6 3 |
| 8041 | Cdrom | Development of Evaluation System of Safety Margin Effects for Degradation of CANDU Reactors Using RELAP-CANDU | 6 5 |
Shripad Revankar, Purdue Univ; , ; , USA; Ph: FAX: E-mail: shripad@purdue.edu
| 8323 | Cdrom | Testing Programs Related to Potential Adverse Flow Effects In Nuclear Power Plants |
| 8262 | Cdrom | The TRAB-SMABRE for 3D Plant Transient and Accident Analyses | 11 |
| 8179 | Cdrom | Analysis of Beyond Design Basis Accidents in Spent Fuel Pools of the Ignalina NPP | 6 9 |
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
| 8429 | Cdrom | Subchannel Analysis of CANDU-SCWR Fuel | 6 1 |
| 8419 | Cdrom | GNF2 Counter-Current Flow Limitation Testing | 1 6 |
| 8270 | Cdrom | Interfacial Momentum Exchange Models Used in Nuclear Reactor System Analysis Codes |
| 8170 | Cdrom | Thermohydrodynamic Analysis of Reactor Vessel Auxiliary Cooling System for Lead-Cooled Battery Omnibus Reactor Integral System | 6 3 |
| 8077 | Cdrom | Development of High Fidelity System Analysis Code for GEN IV Reactors | 6 3 |
| 8012 | Cdrom | Multidimensional Analysis of Developing Two-phase Flows in an ESBWR Chimney with and without Riser Channels | 6 |
Michael A. Shockling, Westinghouse; , ; , USA; Ph: FAX: E-mail: shocklma@westinghouse.com
| 8391 | Cdrom | On the Modeling of Channel-to-Channel Oscillations in Boiling Water Reactors | 6 11 |
| 8137 | Cdrom | Heat Transfer in Intermediate Heat Exchanger under Low Flow Rate Conditions | 6 4 |
| 8121 | Cdrom | Identification of the Relation between Turbulence Coefficient and Local Wall Thinning inside Carbon Steel Piping | 6 4 |
| 8095 | Cdrom | Theoretical and Experimental Study of Steam Condensation Induced Water Hammer Phenomena | 6 9 |
Michael A. Shockling, Westinghouse; , ; , USA; Ph: FAX: E-mail: shocklma@westinghouse.com
| 8286 | Cdrom | Transient Accident Analysis of the Glovebox System in a Large Process Room | 6 5 |
| 8275 | Cdrom | Pressure Drop Characteristics of Cross-Shaped Spiral (CSS) Rod Bundle for LWRs | 6 1 |
| 8225 | Cdrom | Application of the Subchannel Analysis Code MATRA for Low Flow and Low Pressure Conditions | 6 1 |
| 8209 | Cdrom | Optimizing Critical Heat Flux Enhancement through Nanoparticle-Based Surface Modifications | 6 1 |
Meghan E. Leslie, Westinghouse; , ; , USA; Ph: FAX: E-mail: leslieme@westinghouse.com
| 8043 | Cdrom | Applications of Nanofluids to Enhance LWR Accidents Management in In-vessel Retention and Emergency Core Cooling System | 1 6 |
| 8330 | Cdrom | Thermal-fluid Characterization of ZnO Nanofluid for Advanced Nuclear Power Plants | 6 1 |
| 8292 | Cdrom | Evaluation of Crack Opening Area, Leak Rate and Probabilistic Models in CANTIA | 6 6 |
| 8290 | Cdrom | Condensation Correlation for a Vertical Passive Condenser System | 6 6 |
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
| 8127 | Cdrom | Pressure Loss Coefficient Evaluation Based on CFD Analysis for Simple Geometries and PWR Reactor Vessel without Geometry Simplification | 6 6 |
| 8122 | Cdrom | CFD Estimation of the Heat Transfer due to the Natural Convection in a CEA Extension Shaft Guide Tube | 6 |
| 8094 | Cdrom | System / CFD Coupling for Reactor Transient Analysis. An Application to the Gas Fast Reactor with CATHARE and TRIO_U | 6 3 |
| 8062 | Cdrom | A CFD Solver with Variable Gas Properties for Applications to High Temperature Gas Cooled Reactors | 6 |
| 8049 | Cdrom | Free Surface Modeling and Simulation of the Water Experiment for the XT ADS Spallation Target | 6 |
Anne Charmeau, Univ of Florida; , ; , USA; Ph: FAX: E-mail: anne@inspi.ufl.edu
| 8264 | Cdrom | CFD Calculations of the Assembly of VVER-440 type PWR Reactors | 6 1 |
| 8252 | Cdrom | RANS-based CFD Simulations of Wire-Wrapped Fast Reactor Fuel Assemblies | 6 3 |
| 8155 | Cdrom | CFD Predictions of Heat Transfer in the Super Critical Flow Regime | 6 |
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
| 8278 | Cdrom | Study on Coolant Mixing in VVER-440 Fuel Assembly Head | 6 |
| 8265 | Cdrom | Evaluation of the Two-phase Flow Characteristics in the Steam Separator by Using a CFD Code | 6 1 |
| 8212 | Cdrom | k-ε Modeling Using Modified Nodal Integral Method | 6 |
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
| 8333 | Cdrom | Supercritical Water Heat Transfer in a Vertical Bare Tube: Normal, Improved and Deteriorated Regimes | 6 1 |
| 8303 | Cdrom | LWR Containment Safety Research in PANDA | 6 |
| 8229 | Cdrom | Interfacial Area Transport in Horizontal Bubbly Flow with Elbow Restrictions | 6 |
| 8222 | Cdrom | High Temperature Irradiation Resistant Thermocouples A Low Cost Sensor for In-Pile Testing at High Temperatures | 6 8 |
| 8151 | Cdrom | Analysis of Two-Phase Flow and Boiling Heat Transfer in Inclined Channel of Core-catcher | 6 |
| 8441 | Cdrom | Performance and Scaling Analysis for the Two-Phase Natural Circulation | 6.08a |
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
| 8306 | Cdrom | 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 |
| 8310 | Cdrom | 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 |
| 8316 | Cdrom | Development of the Cooling Technology on TRU Fuel Pin Bundle during Fuel Fabrication Process (3) Development of Analytical Tool | 6 3 |
| 8332 | Cdrom | An Assessment of Large-Eddy Simulation for Thermal Fatigue Prediction | 6 |
| 8329 | Cdrom | Experimental Investigation of Crud Deposition under Sub-cooled Boiling Conditions | 6 |
Genevieve Geffraye, CEA; , ; , France; Ph: FAX: E-mail: genevieve.geffraye@cea.fr
| 8322 | Cdrom | Investigation of Heat Transfer for Gas Cooled Systems | 2 6 |
| 8146 | Cdrom | Mixing Process by Natural Convection and Molecular Diffusion of Two Component Gases in a Stable Stratified Fluid Layer | 6 2 |
| 8009 | Cdrom | Design Considerations For Compact Heat Exchangers | 6 2 |
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
Toshikazu Takeda, Osaka University; , ; , Japan; Ph: FAX: E-mail: takeda@nucl.eng.osaka-u.ac.jp
| 8102 | Cdrom | A Contingency Safe, Responsible, Economic, Increased Capacity Spent Nuclear Fuel (SNF) Disposition to Avoid Interference with Yucca Mountain Licensing | 7 |
| 8046 | Cdrom | Market Share Scenarios for Gen-III and Gen-IV Reactors in Europe | 7 9 |
| 8089 | Cdrom | Progress in Development of Erbia-Bearing Super High Burnup Fuel | 7 11 |
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
| 8284 | Cdrom | Radioactive Waste Management in Romania | 7 |
| 8101 | Cdrom | Prospects of Thorium - Fuel Reprocessing for Molten Salt Reactor Systems | 7 3 |
| 8014 | Cdrom | A Study on Methodology of Optimal Characterization and Disposal Priority for Low and Intermediate Level Radioactive Wastes (LILWs) in Korea | 7 |
| 8208 | Cdrom | Development of an Integrated Systems Engineering Modeling Package for Chemical Separation Processes under Advanced Fuel Cycle Initiative | 7 |
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
| 8165 | Cdrom | Development of FR Fuel Cycle in Japan (1) - Development Scope of Fuel Cycle Technology | 7 3 |
| 8161 | Cdrom | 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 |
| 8142 | Cdrom | 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 |
| 8236 | Cdrom | Development of FR fuel cycle in Japan (4) Consideration of Transition from LWR-cycle to FR-cycle | 7 |
Temitope Taiwo, ANL; , ; , USA; Ph: FAX: E-mail: Taiwo@ANL.gov
| 8171 | Cdrom | Evaluation of the Possibility of Plutonium and Minor Actinides Transmutation in HWR | 7 |
| 8174 | Cdrom | Preliminary Analysis by Means of the TRANSURANUS Code of Mixed Oxide Fuel Rod for Gen IV Lead Fast Reactor | 7 3 |
| 8033 | Cdrom | Mixed Plutonium Conversion and Actinides Burning in Fast Molten Salt Reactors | 7 |
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, Energy Solutions; , ; , USA; Ph: FAX: E-mail:rsrinivasan@energysolutions.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
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, Energy Solutions; , ; , USA; Ph: FAX: E-mail: rsrinivasan@energysolutions.
