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Booklet of the Official Program (PDF, 2.56MB)
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May 10-14, 2009 · Shinjuku, Tokyo · Keio Plaza Hotel Tokyo
Each speaker name is linked to his/her presentation material PDF file.
If you have any difficulty to open the PDF file directly, please try opening it locally after downloading it to your local computer file.
| Opening: Opening Plenary Session | ||
| Monday 11 May, 8:45-10:40, 5F 'EMINENCE HALL' | ||
| Co-Chair: |
Yoshiaki Oka (The University of Tokyo, Japan) David Hill (INL, USA) |
|
| Address: | Yasuhiro Nakasone (Former Prime Minister of Japan) | |
| Speaker: |
Shunsuke Kondo (AEC, Japan) Carter Savage (DOE, USA) Hiroshi Morimoto (FEPC, Japan) Philippe Pradel (CEA, France) |
|
| Plenary: New Plant Deployment | ||
| Monday 11 May, 11:00-12:30, 5F 'EMINENCE HALL' | ||
| Co-Chair: |
Takuya Hattori (JAIF, Japan) Thomas O'Neil (Exelon Energy, USA) |
|
| Speaker: |
Osamu Maekawa (Toshiba, Japan) Arnaud de Bourayne (AREVA, France) Jack Fuller (GE-Hitachi, USA) Kiyoshi Yamauchi (MHI, Japan) |
|
| Panel-1: Regulatory Program and Strategies | ||
| Monday 11 May, 14:00-15:45,4F-Room 'NISHIKI' | ||
| Co-Chair: |
Shojiro Matsuura (NSRA, Japan) Jukka Laaksonen (STUK, Finland) |
|
| Speaker: |
Jukka Laaksonen (STUK, Finland) Yasuhisa Komoda (NISA, Japan) Peter Lyons (NRC, USA) Marie-Pierre Comets (ASN, France) Jong-In Lee (KINS, Korea) |
|
| Panel-2: Nuclear Fuel Cycle and Sustainability | ||
| Monday 11 May, 16:00-17:45, 4F-Room 'OHGI' | ||
| Co-Chair: |
Kenji Yamaji (The University of Tokyo, Japan) Philippe Pradel (CEA, France) |
|
| Speaker: |
Harukuni Tanaka (JNFL, Japan) Shigeo Nomura (JAEA, Japan) Dominique Ochem (CEA, France) Phillip Finck (INL, USA) H. S. Kamath (BARC, India) |
|
| Panel-3: Globalization of Nuclear Energy | ||
| Tuesday 12 May, 8:45-10:30, 4F-Room 'NISHIKI' | ||
| Co-Chair: |
Kazuaki Matsui (IAE, Japan) Mujid S. Kazimi (MIT, USA) |
|
| Speaker: |
Akira Omoto (IAEA) Thomas Sanders (SNL, USA) Yoichiro Shimazu (Hokkaido University, Japan) Thierry Dujardin (OECD/NEA) Kenji Kimura (METI, Japan) |
|
| Panel-4: Future Reactor & Fuel Cycle-1 | ||
| Tuesday 12 May, 10:45-12:30, 4F-Room 'OHGI' | ||
| Co-Chair: |
Takashi Nagata (JAEA, Japan) Moon Hee Chang (KAERI, Korea) |
|
| Speaker: |
Raymond Furstenau (DOE, USA) Regis A. Matzie (WH, USA) Takamichi Iwamura (JAEA, Japan) Keizo Okada (MFBRS, Japan) Frank Carre (CEA, France) Dohee Hahn (KAERI, Korea) |
|
| Panel-5: Future Reactor & Fuel Cycle-2 | ||
| Tuesday 12 May, 13:40-15:45, 4F-Room 'NISHIKI' | ||
| Co-Chair: |
Ichiro Ikemoto (CRIEPI, Japan) Regis A. Matzie (WH, USA) |
|
| Speaker: |
Thierry Nkaoua (AREVA, France) Yoon Chang (ANL,USA) S. Raghupathy (IGCAR, India) Evgeny V. Kusmartsev (OKBM, Russia) Kazuo Arie (Toshiba, Japan) Dorothy Davidson (AFS, USA) |
|
| Panel-6: Developing the Global Nuclear Market | ||
| Tuesday 12 May, 16:00-18:25, 4F-Room 'OHGI' | ||
| Co-Chair: |
Akira Omoto (IAEA) Jean-Claude Gauthier (AREVA, France) |
|
| Speaker: |
Nobutaka Wachi (JAPC, Japan) Thomas O'Neil (Exelon Energy, USA) Kee-Cheol Park (KHNP, Korea) Alf Bjorseth (SCATECH AS, Norway) Kamol Takabut (Electricity Generating Authority of Thailand, Thailand) |
|
| Panel-7: | Human Resources | |
| Wednesday 13 May, 10:00-12:05, 4F-Room 'NISHIKI' | ||
| Co-Chair: |
Tadashi Narabayashi (Hokkaido University, Japan) Samim Anghaie (University of Florida, USA) |
|
| Speaker: |
Yoshiaki Oka (The University of Tokyo, Japan) John Tuohy (ANS, USA) Yonezou Tsujikura (FEPC, Japan) Josseline de Claussade (AREVA, France) Shinzo Saito (Former AEC, Japan) Mamoru Ishii (Purdue University, USA) |
|
*: Extended Abstract
| Track 1: Water-Cooled Reactor Programs and Issues (6 sessions) | ||||
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1-1 BWR (1) May 11 (Mon.), 4F-Room 'KEYAKI', 14:00 - 15:30 Chair: T. Okubo (JAEA), T. A. Mathews (AREVA) |
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| 9459 : | The SWR 1000 Customer-Operator Partnership: A Common Project Boiling Water Reactor Developed Jointly ofby AREVA NP and E.ON Kernkraft D. Pasler, J. Gauthier (AREVA), F. Diercks, M. Fuchs (E.ON Kernkraft GmbH) |
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| 9088 : | Development of BWR Ex-core Nuclear Instrumentation System -- Experimental Verification of Ex-core Local Power Monitoring Method by Using Neutron Streaming Pipes -- S. Naito, M. Takemura, H. Kumanomido, K. Yoshioka, S. Sakurai, Y. Goto, Y. Karino, M. Izumi (Toshiba) |
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| 9139 : | Thermal-Hydraulic Stability of Natural Circulation BWR under Startup – Flashing Effects R. Hu, M. Kazimi (MIT) |
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| 9528 : | OHMA full MOX-ABWR T. Ihara (JPOWER), M. Sasagawa (GNF-J), Y. Iwata (Hitachi-GENE) |
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1-2 BWR (2) May 11 (Mon.), 4F-Room 'KEYAKI', 15:45 - 17:15 Chair: K. Hiraiwa (Toshiba), B. Petrovic (Georgia Tech) |
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| 9022 : | Breeder-type Operation based on the LWR-MOX Fuel Technologies in Light Water Reactors with Hard Neutron Spectrum (FLWR) S. Uchikawa, T. Okubo, Y. Nakano (JAEA) |
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| 9304 : | Neutronic Characteristics of FLWR in the Transition Phase Changing from High Conversion Core to Breeder Core H. Akie, Y. Nakano, T. Okubo (JAEA) |
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| 9092 : | Evaluation of Uncertainties in FEMAXI-6 Calculations for Predicting MOX Fuel Behaviors in FLWR design A. Yamaji, M. Suzuki, T. Okubo (JAEA) |
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| 9071 : | General consideration on effective Pu utilization in future LWRs N. Ishikawa, T. Okubo (JAEA) |
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1-3 PWR (1) May 12 (Tue.), 4F-Room 'KEYAKI', 09:00 - 10:30 Chair: S. Otsuka (MHI), Y. Okabe (ATMEA) |
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| * 9116 : | Superior Operation Performance of ATMEA1 Y. Okabe (ATMEA) |
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| 9140 : | Design Control for Standard U.S. EPR Plants T. A. Mathews, M. Miller (AREVA) |
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| 9061 : | EPR™ engineered features for core melt mitigation in severe accidents M. Fischer, A. Henning (AREVA) |
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| 9196 : | MELT SPREADING CODE ASSESSMENT, MODIFICATIONS, AND INITIAL APPLICATION TO THE EPR CORE CATCHER DESIGN M. T. Farmer (ANL), S. Basu (USNRC) |
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| 9335 : | US-APWR Human Systems Interface System Verification & Validation Results; Application of the Mitsubishi Advanced Design to the US Market R. E. Hall (RTS), J. Easter (PLC), E. Roth (Roth Cognitive Engineering), L. Kabana (GTTS), K. Mashio (MHI), K. Takahashi (MELCO), T. Clouser (Luminant Power) |
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1-4 PWR (2) May 12 (Tue.), 4F-Room 'KEYAKI', 10:45 - 12:15 Chair: S. Otsuka (MHI), Y. Okabe (ATMEA) |
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| 9087 : | Main Features of Modern Russian Design of NPP with High Power VVER Reactors (AES-2006 Design) S. Svetlov, A. Altshuller, A. Molchanov, A. Kazarin (SPAEP) |
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| 9154 : | Competitiveness of Small-Medium Reactors: a probabilistic study on the economy of scale factor A. Trianni, G. Locatelli, P. Trucco (PoliMi) |
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| 9204 : | IRIS-50: A 50 MWe Advanced PWR Design for Smaller Regional Grids and Specialized Applications B. Petrovic (Georgia Tech), M. Carelli, L. Conway, R. Hundal (WEC), E. Barbaso, F. Gamba (PoliTo), M. Centofante (PoliMi) |
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| 9067 : | Calculation of axial xenon-oscillations in the HPLWR T. Reiss, S. Fehér, S. Czifrus (BUTE) |
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|
1-5 Common (1) May 12 (Tue.), 4F-Room 'KEYAKI', 14:00 - 15:30 Chair: T. A. Mathews (AREVA), S. Otsuka (MHI) |
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| 9182 : | On the Evolution of the Regulatory Guidance for Seismic Qualification of Electric and Active Mechanical Equipment for Nuclear Power Plants C. H. Ng, P. Chen (US NRC) |
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| 9273 : | Bandwidth of Reactor Internals Vibration Resonance with Coolant Pressure Oscillations K. Proskuryakov, K. Novikov, E. Galivec (MPEI) |
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| 9275 : | Sound Velocity in the Coolant of Boiling Nuclear Reactors K. Proskuryakov, D. Parshin, K. S. Novikov, E. Y. Galivec (MPEI) |
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| 9241 : | Logic Qualification of FPGA-Based Safety-Related I&C Systems T. Hayashi, N. Oda, T. Ito, T. Miyazaki, Y. Haren (Toshiba) |
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|
1-6 Common (2) May 12 (Tue.), 4F-Room 'KEYAKI', 15:45 - 17:15 Chair: H. Heki (Toshiba), S. Bilbao y Leon (IAEA) |
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| 9481 : | Advanced Construction Methods for New Nuclear Power Plants S. Bilbao y Leon, S. Moon, A. Rao, B. Tyobeka, J. Cleveland (IAEA) |
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| * 9529 : | DEVELOPMENT OF NEXT GENERATION LIGHT WATER REACTOR IN JAPAN (1) K. Tsuzuki, T. Shiotani, I. Ohno, S. Kasai (IAE) |
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| * 9530 : | DEVELOPMENT OF NEXT GENERATION LIGHT WATER REACTOR IN JAPAN (2) T. Yamamoto, Y. Ohga, T. Kurosaki (IAE), S. Shimizu (MHI), H. Soneda (Hitachi-GENE), K. Hiraiwa (Toshiba) |
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| * 9531 : | Development of Next Generation Light Water Reactor in Japan (3) Y. Ohga, T. Yamamoto, T. Kurosaki (IAE), M. Matsuura (Hitachi-GENE), S. Shimizu (MHI), A. Murase (Toshiba) |
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| Track 2: High Temperature Gas Cooled Reactors and Hydrogen Production (7 sessions) | ||||
|
2-1 HTR Concepts and Design Innovations (1) May 11 (Mon.), 42F-Room 'FUJI', 14:00 - 15:30 Chair: C. Oh (INL) |
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| 9234 : | Assessments of Beyond Design Basis Accidents with Air Ingress into a Block-Type VHTR Core M. Richards (GA), E. Takada, N. Tsuji, M. Nakano, K. Ohashi (FES) |
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| 9383 : | Effects of a Graphite Aerosol on Coupled Radiation-Convection Heat Transfer in the HTGR Reactor Cavity Cooling System B. Ahmed, A. Charmeau, S. Anghaie (Univ. of Florida) |
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| 9427 : | Graphite Oxidation and Structural Strength of Graphite Support Column in VHTR B. Park, H. No (KAIST), E. Kim, C. Oh (INL) |
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|
2-2 HTR Concepts and Design Innovations (2) May 11 (Mon.), 42F-Room 'FUJI', 15:45 - 17:15 Chair: P. Dumaz (CEA) |
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| 9146 : | Effect of Channel Configurations for Tritium Transfer in Printed Circuit Heat Exchangers C. Oh, E. S. Kim, R. Shrake (INL) |
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| 9441 : | Effect of Reacting Surface Density on the Overall Graphite Oxidation Rate C. Oh, E. Kim (INL), J. Lim (Univ. of Tokyo), R. Schultz, D. Petti (INL) |
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| 9443 : | Phenomena Identification Ranking Table and Knowledge Base Gaps and Needs for the Modular High-Temperature Gas-Cooled Reactor A. Tokuhiro, G. Potirniche, K. Rink (Univ. of Idaho) |
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| 9471 : | Artificial Neural Networks versus Genetic Algorithms in Thermohydraulics for Energy Conversion System Design Optimization A. Tokuhiro, A. Ridluan, O. Linda, M. Manic (Univ. of Idaho) |
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| 9473 : | Design Optimization of a NGNP Candidate Heat Exchanger with Cost Model A. Tokuhiro, A. Ridluan, W. Danchus (Univ. of Idaho) |
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|
2-3 HTR Concepts and Design Innovations (3) May 12 (Tue.), 42F-Room 'FUJI', 09:00 - 10:30 Chair: A. Tokuhiro (Univ. of Idaho) |
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| 9073 : | HTGR Core and Structural Integrity Study for Longer Burnup Cycle M. Nakano, N. Tsuji (Fuji) |
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| 9123 : | ANALYSIS OF THE POROUS STRUCTURE OF AN ANNULAR PEBBLE BED REACTOR W. Van Antwerpen, J. Du Toit, P. Rousseau (North West Univ.) |
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| 9124 : | ACCOUNTING FOR POROUS STRUCTURE IN EFFECTIVE THERMAL CONDUCTIVITY CALCULATIONS IN A PEBBLE BED REACTOR W. Van Antwerpen, J. Du Toit, P. Rousseau (North West Univ.) |
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| 9476 : | Contribution to Improvement of HTGR Technology by Using HTTR Operation Data S. Nakagawa, D. Tochio, M. Shinohara, N. Nojiri, T. Nishihara, M. Goto, K. Takamatsu (JAEA) |
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2-4 Modeling and Simulation of GCRs May 12 (Tue.), 42F-Room 'FUJI', 10:45 - 12:15 Chair: M. Nakano (Fuji) |
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| 9014 : | Investigating the Thermal-Hydraulic Characteristics in the HTGR core using a transient CFD model C. T. Chen, Y. Ferng, C. C. Chieng, B. S. Pei (NTHU) |
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| 9046 : | HTR Fuel Modeling with the ATLAS Code: Thermal mechanical Behavior and Fission Product Release Assessment P. Guillermier, L. Daniel (AREVA), L. Gauthier (CEA) |
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| 9091 : | Optimization of Inlet Plenum of A PBMR Using Surrogate Modeling S. Lee, K. Kim (Inha Univ.) |
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| 9205 : | Comparison of GAMMA Results with Experimental Data in the Naturally Circulating Gas Loop J. Lee, H. No (KAIST) |
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| 9409 : | Analysis for HTTR Burnup Characteristics M. Goto, N. Fujimoto, S. Nakagawa (JAEA) |
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| 9446 : | Validation of CFD Modeling for VGM Loss-of-Forced-Cooling Accidents A. Wysocki, B. Ahmed, A. Charmeau, S. Anghaie (Univ. of Florida) |
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|
2-5 GFR and Other Advanced Concepts May 12 (Tue.), 42F-Room 'FUJI', 14:00 - 15:30 Chair: S. Nakagawa (JAEA) |
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| 9062 : | GFR Demonstrator ALLEGRO Design Status C. Poette, J. Malo, V. Brun-Magaud, F. Morin, I. Dor, B. Mathieu (CEA), H. Duhamel (COMEX Nucleaire), R. Stainsby (AMEC), K. Mikityuk (PSI) |
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| 9063 : | Design of a Supercritical Carbon Dioxide Cooled Reactor for Marine Applications S. Jewer, M. Wilson (DCMT), T. Verchère, T. Pâris de Bollardière (EAMEA), P. O’Sullivan, S. Heap, A. Thompson, P. Beeley (DCMT) |
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| 9109 : | Gas Cooled Fast Reactor 2400 MWTh, status on the conceptual design studies and preliminary safety analysis J. Malo, N. Alpy, F. Bentivoglio, F. Bertrand, L. Cachon, G. Geffraye, D. Haubensack, A. Messie, F. Morin, Y. Peneliau, D. Plancq, F. Pra, P. Richard (CEA) |
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| 9152 : | Supercritical CO2 Test Loop Operation and First Test Results S. A. Wright, P. S. Pickard (SNL) |
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| 9225 : | Design of Multi-input Multi-output Controller for Magnetic Bearing which Suspends Helium-Turbine Generator Rotor for High Temperature Gas cooled Reactor S. Takada, Y. Funatake, Y. Inagaki (JAEA) |
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2-6 HTR Fuel and High Temperature Materials May 12 (Tue.), 42F-Room 'FUJI', 15:45 - 17:15 Chair: S. Takada (JAEA) |
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| 9069 : | Diffusion Bonding in Compact Heat Exchangers D. Southall, S. J. Dewson (Meggitt - Heatric) |
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| 9149 : | Application of X-Ray imaging for HTR fuel characterization P. Guillermier, D. Tisseur, J. Banchet, M. Taglione (AREVA), M. Perez (CEA), J. Letang (INSA Lyon) |
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| 9333 : | An Experimental Study on the Flow and Heat Transfer of Flinak Molten Salt in Small Channels for the Application to the VHTR Intermediate Heat Exchanger K. Bang, I. Hwang, H. Jeong, K. Kim (KMU) |
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| 9466 : | Design of the Next Generation Nuclear Plant Graphite Creep Experiment for Irradiation in the Advanced Test Reactor S. B. Grover (INL) |
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2-7 Power Conversion Systems and Non-Electric Applications May 13 (Wed.), 42F-Room 'FUJI', 09:00 - 10:30 Chair: M. A. Fütterer (JRC-IE) |
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| 9294 : | Research and Development on IS Process Components for Hydrogen Production. (I) Test-fabrication of Sulfuric Acid Transfer Pump J. Iwatsuki, A. Terada (JAEA), Y. Watanabe (Tohoku Univ.), R. Hino, S. Kubo, K. Onuki (JAEA) |
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| 9291 : | Research and Development on IS Process Components for Hydrogen Production (II) Corrosion Resistance of Glass Lining in High Temperature Sulfuric Acid N. Tanaka, J. Iwatsuki, S. Kubo, A. Terada, K. Onuki (JAEA) |
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| 9417 : | Experimental Studies of an optimal operating condition for the Bunsen process in the I–S thermochemical cycle H. Yoon, H. No, B. Lee, H. Jin, Y. Kim, J. Lee (KAIST) |
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| 9406 : | Optimization of The Hybrid Sulfur Cycle for Nuclear Hydrogen Production using UniSim Design Y. Jung, Y. Jeong (KAIST) |
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| 9351 : | Cogeneration Using a Nuclear Reactor to Generate Process Heat G. Alonso, J. R. Ramirez (ININ) |
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| 9524 : | EVALUATION FOR INDIRECT CCGT AND STEAM CYCLE IN HIGH TEMPERATURE GAS COOLED REACTOR PLANT FROM THE VIEWPOINT OF PLANT DYNAMICS AND CONTROLLABILITY I. Minatsuki, Y. Mizokami (MHI), D. Hittner, D. Petit (AREVA) |
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| Track 3: LMFR & Longer Term Reactor Programs (12 sessions) | ||||
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3-1 Supercritical-Pressure Water-Cooled Fast Reactor (1) May 11 (Mon.), 42F-Room 'TAKAO', 14:00 - 15:30 Chair: T. Iwamura (JAEA), J. Strflinger (FZK) |
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| 9257 : | Loss of coolant accident analysis of a Supercritical-Pressure Water-Cooled Fast Reactor with downward flow channels S. Ikejiri, Y. Ishiwatari, Y. Oka (Univ. of Tokyo) |
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| 9261 : | DESIGN AND IMPROVEMENT OF PLANT CONTROL SYSTEM FOR A SUPER FAST REACTOR Y. Ishiwatari, C. Peng, T. Sawada, S. Ikejiri, Y. Oka (Univ. of Tokyo) |
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| 9262 : | CFD Analyses in Tight-Lattice Subchannels and Seven-Rods Bundle geometries of a Super Fast Reactor J. Gou, Y. Ishiwatari, Y. Oka, M. Yamakawa, S. Ikejiri (Univ. of Tokyo) |
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| 9263 : | Evaluation of Transmutation Performance of Long-Lived Fission Products with a Super Fast Reactor H. Lu, Y. Ishiwatari, C. Han, Y. Oka, S. Ikejiri (Univ. of Tokyo) |
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3-2 Supercritical-Pressure Water-Cooled Fast Reactor (2) May 11 (Mon.), 42F-Room 'TAKAO', 15:45 - 17:15 Chair: Y. Okano (JAEA), P. Hejzlar (MIT) |
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| 9264 : | Core design and fuel rod analyses of a Super Fast Reactor with high power density H. Ju, L. Cao, Y. Ishiwatari, H. Lu, Y. Oka, S. Ikejiri (Univ. of Tokyo) |
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| 9265 : | Thermal and Stability Considerations for a Supercritical Water-cooled Fast Reactor during Power-Raising Phase of Plant Startup J. Cai, Y. Ishiwatari, S. Ikejiri, Y. Oka (Univ. of Tokyo) |
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| 9268 : | Results of the Mid-Term Assessment of the High Performance Light Water Reactor Phase 2 Project J. Starflinger, T. Schulenberg (FZK), P. Marsault (CEA), D. Bittermann (AREVA), C. Maraczy (AEKI), E. Laurien (USTUTT), J. Lycklama (NRG), H. Anglart (KTH), M. Andreani (PSI), M. Ruzickova (UJV), L. Heikinheimo (VTT) |
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| 9391 : | Deterioration of Heat Transfer in Upward Flowing Supercritical Pressure Water J. R. Licht, M. Anderson, M. Corradini (UW) |
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| 9187 : | Design Concept of the HPLWR Moderator Flow Path C. Koehly, T. Schulenberg, J. Starflinger (FZK) |
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3-3 4S Series(1) May 12 (Tue.), 42F-Room 'TAKAO', 09:00 - 10:30 Chair: T. Mizuno (JAEA), D. Hahn (KAERI) |
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| 9214 : | Development of the 4S and related technologies (1); Plant System Overview and Current Status Y. Tsuboi, S. Kasuga, Y. Sakashita, H. Matsumiya, K. Hasegawa (Toshiba), N. Ueda (CRIEPI), A. Grenci (WEC), N. Handa (Toshiba) |
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| 9195 : | Long Life Metallic Fuel A. M. Yacout (ANL), Y. Tsuboi (Toshiba), N. Ueda (CRIEPI) |
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| 9200 : | Development of 4S and related technologies (3) Statistical Evaluation of Safety Performance of 4S on ULOF Event K. Ishii, H. Matsumiya, H. Horie, K. Miyagi (Toshiba) |
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| 9162 : | Development of 4S and Related Technologies (4) Comparison of Transient Accident Sequences Between the SAS4A/SASSYS-1 and CERES Reactor System Analysis Codes T. H. Fanning, F. E. Dunn (ANL), Y. Nishi (CRIEPI) |
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3-4 4S Series(2) May 12 (Tue.), 42F-Room 'TAKAO', 14:00 - 15:30 Chair: Y. Ishiwatari (Univ. of Tokyo), G. Fiorini (CEA) |
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| 9076 : | Development of 4S and related technologies(5) THERMAL HYDRAULICS ANALYSIS OF REACTOR TRIP EVENT H. Watanabe, A. Matsuda (Toshiba) |
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| 9493 : | DEVELOPMENT OF THE 4S AND RELATED TECHNOLOGIES (7) SUMMARY OF THE FCA XXIII EXPERIMENT ANALYSES TOWARDS EVALUATION OF PREDICTION ACCURACIES FOR THE 4S CORE CHARACTERISTICS N. Ueda (CRIEPI), M. Fukushima, S. Okajima (JAEA), T. Tekeda, T. Kitada (Osaka Univ.), Y. Nauchi, I. Kinoshita, T. Matsumura (CRIEPI) |
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| 9166 : | Development of 4S and Related Technologies (7) – Analytical Evaluation of RVACS Performance under Loss of Stacks Condition – S. Nishimura, Y. Nishi, N. Ueda (CRIEPI) |
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| 9184 : | Development of 4S and related technologies (8) An application of physics benchmark experiment results to safety analyses of small fast reactors -- An analysis of delayed neutron fraction benchmark results using nuclear design methodology -- M. Kawashima (TNES), Y. Tsuboi, S. Matsuyama (Toshiba) |
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3-5 JSFR Series May 12 (Tue.), 42F-Room 'TAKAO', 15:45 - 17:15 Chair: K. Okamoto (Univ. of Tokyo) |
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| 9298 : | Conceptual Design for Japan Sodium-Cooled Fast Reactor (1): Current Status of System Design for JSFR N. Uto, T. Sakai, T. Mihara (JAEA), M. Toda (MFBR), S. Kotake, K. Aoto (JAEA) |
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| 9296 : | Conceptual Design of Japan Sodium-Cooled Fast Reactor (2) Thermal-Hydraulic Design for Reactor Upper Sodium Plenum in JSFR K. Ohyama, O. Watanabe (MFBR), H. Yamano (JAEA) |
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| 9281 : | Conceptual Design for Japan Sodium-Cooled Fast Reactor (3): Development of advanced fuel handling system for JSFR A. Katoh, S. Hirata, Y. Chikazawa, N. Uto (JAEA), H. Obata, S. Kotake (JAPC) |
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| 9418 : | Conceptual Design for Japan Sodium-Cooled Fast Reactor (4): Developmental study of Steel Plate Reinforced Concrete Containment Vessel for JSFR T. Hosoya (JAEA), K. Satoh (MFBR), T. Somaki (Obayashi), I. Matsuo (Kajima), K. Shimizu (MHI), K. Negishi (JAEA) |
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3-6 SFR Design Concept (1) May 13 (Wed.), 42F-Room 'TAKAO', 09:00 - 10:30 Chair: Y. Chikazawa (JAEA), Y. Kwon (KAERI) |
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| 9027 : | Design Considerations for Economically Competitive Sodium Cooled Fast Reactors H. Zhang, H. Zhao, V. Mousseau (INL) |
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| 9064 : | EUROPEAN COMMISSION - 7TH FRAMEWORK PROGRAMME : THE COLLABORATIVE PROJECT ON EUROPEAN SODIUM FAST REACTOR (CP ESFR) G. Fiorini (CEA) |
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| 9402 : | Study of an Electromagnetic Pump applied to a Primary Main Pumps of Large Scale Sodium Cooled Reactor K. Aizawa, S. Kotake, A. Kuniaki (JAEA), H. Araseki (CRIEPI), R. Aizawa, H. Ota (Toshiba) |
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| * 9455 : | Status of Advanced SFR Concept Design Studies at KAERI D. Hahn, Y. Kim (KAERI) |
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| 9041 : | Approach to Design of Future FBRs with Enhanced Safety and Economy R. S, B. V, P. P, S. P, C. P, C. S.C, B. Raj (IGCAR) |
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3-7 SFR Design Concept (2) May 13 (Wed.), 42F-Room 'TAKAO', 10:45 - 12:15 Chair: Y. Tsuboi (Toshiba), H. Zhang (INL) |
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| 9004 : | Cross-cutting CFD Support to Innovative Reactor Design F. Roelofs (NRG) |
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| 9105 : | EVALUATION OF ALTERNATIVE FLUIDS FOR SFR INTERMEDIATE LOOPS L. Brissonneau, N. Simon, F. Baqué, M. Saez, F. Balbaud, D. Rochwerger (CEA), A. Gerber (AREVA), G. Prèle, A. Capitaine (EDF), G. Rodriguez (CEA) |
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| 9198 : | Steam producing plant concept of 4S for oil sand extraction S. Matsuyama, Y. Nishiguchi, Y. Sakashita, S. Kasuga, M. Kawashima (Toshiba) |
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| 9206 : | Passive Safety Design Characteristics of the KALIMER-600 Burner Reactor Y. Kwon, H. Jeong, C. Cho, K. Ha, H. Song, S. Kim (KAERI) |
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| * 9342 : | Progress on Traveling-Wave Reactor Design J. Gilleland (TerraPower LLC) |
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|
3-8 Neutronics and Core Design May 13 (Wed.), 42F-Room 'TAKAO', 14:00 - 15:30 Chair: T. Aoyama (JAEA), K. D. Weaver (TerraPower LLC) |
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| 9065 : | Generation IV Sodium Fast Reactor: Feedbacks reactivity coefficients role and optimisation to improve safe natural core behaviour during accidental transients A. G. Zaetta, B. Bernardin , M. Vanier , J. Tommasi , F. Varaine (CEA) |
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| 9160 : | Enhanced minor actinide burning core for closed fuel cycle K. Ikeda (MFBR), W. Nakazato (MHI), J. W. Maddox (AREVA), S. Kunishima (MNES) |
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| 9244 : | ELSY Neutronic Analysis by deterministic and Monte Carlo methods: an innovative concept for the control rod systems C. Artioli, M. Sarotto (ENEA), G. Grasso (UniBo), J. Krepel (PSI) |
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| 9384 : | Neutronic Analysis of Two-Fluid Thorium Molten Salt Reactor J. Frýbort, R. Vočka (NRI) |
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| 9525 : | Analysis on Small Long Life Reactor using Thorium Fuel for Water Cooled and Metal Cooled Reactor Types S. Permana (TIT) |
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|
3-9 Core Design and Cycle Analysis May 13 (Wed.), 42F-Room 'TAKAO', 15:45 - 17:15 Chair: Y. Nauchi (CRIEPI) |
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| 9121 : | Effects of Conversion Ratio Change on Core Performances in Medium to Large TRU Burning Reactors H. Song, S. Kim, J. Yoo, Y. Kim (KAERI) |
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| 9226 : | SFR equilibrium cycle analysis with the EQL3D procedure J. Krepel, K. Mikityuk, K. Sun (PSI), G. Rimpault (CEA) |
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| 9288 : | Fast Reactor Core Design Studies to Cope with TRU Fuel Composition Changes in the LWR-to-FBR Transition Period K. Kawashima, S. Maruyama, S. Ohki, T. Mizuno (JAEA) |
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| 9300 : | TRU Composition Changes and their Influence on FBR Core Characteristics in the LWR-to-FBR Transition Period S. Maruyama, S. Ohki, T. Mizuno (JAEA) |
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| 9419 : | A Preliminary Comprehensive Dynamic Analysis of the Typical FaCT Scenarios with JSFR and Related Fuel Cycle Facilities H. Shiotani, K. Ono, T. Ogawa, Y. Koma, K. Kawaguchi (JAEA) |
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|
3-10 Fuels and Materials for SFR May 13 (Wed.), 42F-Room 'FUJI', 10:45 - 12:15 Chair: K. Ikeda (MFBR), C. Jang (KAIST) |
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| 9033 : | Subchannel Analysis of Sodium-Cooled Reactor Fuel Assemblies with Annular Fuel Pins M. J. Memmott, J. Buongiorno, P. Hejzlar (MIT) |
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| 9178 : | High Burn-up Fuels for Fast Reactors: Past Experience and Novel Applications K. D. Weaver (TerraPower LLC) |
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| 9151 : | MATERIALS CHALLENGES SUPPORTING NEW SODIUM FAST REACTOR DESIGNS O. Gelineau, S. Dubiez-le Goff (AREVA), P. Dubuisson (CEA), M. Blat (EDF) |
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| 9194 : | Study on an innovative Fast Reactor utilizing Hydride Neutron Absorber – Development of coating technique on cladding inner surface – T. Kido, K. Itoh (NDC), A. Suzuki (Univ. of Tokyo), Y. Matsumura (Tokai Univ.), K. Konashi (Tohoku Univ.) |
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| 9277 : | Modeling of constituent redistribution and fission product migration in fast reactor metallic fuels Y. Kim, G. L. Hofman, A. M. Yacout (ANL) |
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| 9097 : | Preliminary Structural Integrity Evaluations for the Elevated Temperature Piping of the SFR IHTS against Typical Level A Service Events C. Park, J. Kim, J. Lee (KAERI) |
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|
3-11 Steam Generators and Coolant Technology May 13 (Wed.), 42F-Room 'FUJI', 14:00 - 15:30 Chair: M. Takahashi (TIT) |
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| 9078 : | Development of an Acoustic Steam Generator Leak Detection System Using Delay-and-sum Beamformer Y. Chikazawa (JAEA) |
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| 9169 : | A Study on LMFBR Steam Generator Design without Tube Failure Propagation in Water Leak Events S. Futagami, H. Hayafune (JAEA), K. Fujimura (JAPC), M. Sato (MFBR) |
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| * 9362 : | Development of an innovative plate-type SG for sodium cooled fast reactor - crack propagation at the bonding surface - Y. Nishi, I. Kinoshita (CRIEPI) |
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| * 9283 : | Study on the corrosion behavior of steels in a stagnant lead-bismuth eutectic (LBE) J. Choi, B. Choi, J. Kim, B. Kim (KAERI) |
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|
3-12 Brayton Cycles and Coolant Technology May 13 (Wed.), 42F-Room 'FUJI', 15:45 - 17:15 Chair: Y. Nishi (CRIEPI) |
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| 9026 : | Use of Multiple Reheat Helium Brayton Cycles to Eliminate the Intermediate Heat Transfer Loop for Advanced Loop Type SFRs H. Zhao, H. Zhang, S. E. Bays (INL) |
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| 9077 : | Design, Fabrication and Test Plan of Small Centrifugal Compressor Test model for a Supercritical CO2 Compressor in the Fast Reactor Power Plant Y. Muto, T. Ishizuka, M. Aritomi (TIT) |
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| 9112 : | Development of Sodium Leak Detection Technology Using Laser Resonance Ionization Mass Spectrometry - Design and Functional Test Using Prototype Sodium Detection System - T. Aoyama (JAEA), K. Okazaki (Toshiba), C. Ito, H. Harano (JAEA), K. Watanabe, T. Iguchi (Nagoya Univ.) |
|||
| 9390 : | Real-time Algorithms for the Measurement of Liquid Metal Coolant Flow Velocity with Correlated Thermal Signals T. Moazzeni, Y. Jiang, J. Ma (UNLV) |
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| Track 4: Operation, Performance & Reliability Management (7 sessions) | ||||
|
4-1 Topics on Kashiwazaki-Kariwa Nuclear Power Station May 11 (Mon.), 43F-Room 'STAR LIGHT', 14:00 - 15:30 Chair: T. Narabayashi (Hokkaido Univ.) |
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| * 9398 : | Lessons Learned from Operational Experience of the Chuetsu-Oki Earthquake and New Training Program Development H. Tomita, T. Serizawa, K. Terazu (TEPCO), K. Iwatare, K. Noji (BTC) |
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| 9404 : | Actions at Kashiwazaki Kariwa Nuclear Power Station after the Niigataken Chuetsu-oki Earthquake S. Orita (TEPCO) |
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| * 9405 : | Control Rod Uncoupling at Kashiwazaki Kariwa #6 M. Kawasaki, S. Yamaguchi (TEPCO) |
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| * 9408 : | Planning rational inspection for the Niigata Chuetsu-Oki earthquake at the Kashiwazaki-Kariwa nuclear power plant K. Nishioka (TEPCO) |
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| 9435 : | The Ageing degradations and the earthquake experience A. Shima (TEPCO) |
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|
4-2 Performance and Reliability Improvements (1) May 11 (Mon.), 43F-Room 'STAR LIGHT', 15:45 - 17:15 Chair: C. Chang (INER), M. Tsuji (Hokkaido Univ.) |
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| 9012 : | A new strategy of axila power distribution control based on three axial offsets concept Y. Shimazu (Hokkaido Univ.) |
|||
| 9031 : | Using Neuro-Fuzzy Based Method to Develop Nuclear Turbine Cycle Model Y. Chan, C. Chang (INER) |
|||
| * 9120 : | A Comparative Study on the Reliability Criteria Determination D. Jerng, T. Ju (NETEC) |
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|
4-3 Performance and Reliability Improvements (2) May 12 (Tue.), 43F-Room 'STAR LIGHT', 09:00 - 10:30 Chair: G. Vieru (INR), M. Nagase (Hitachi-GENE) |
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| 9254 : | KHNP Special Safety Review S. Lee, T. Lee, B. Lee (KHNP), G. Park (SNU) |
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| 9287 : | Artificial Neural Network with Self-Organizing Mapping for Reactor Stability Monitoring M. Okumura, M. Tsuji, Y. Shimazu (Hokkaido Univ.) |
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| 9485 : | A New Approach for reduction of the Recontamination after the Chemical Decontamination T. Ito, H. Hosokawa (Hitachi), M. Nagase, M. Sakashita, M. Fuse (Hitachi-GENE) |
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| * 9520 : | Safety Culture Assessment Developed by JANTI J. Hamada (JANTI) |
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|
4-4 Risk-based Maintenance and Life Cycle Management May 12 (Tue.), 43F-Room 'STAR LIGHT', 10:45 - 12:15 Chair: K. Moriya (Hitachi-GENE), G. Vieru (INR) |
||||
| 9094 : | Development of a SPV Management Program for Nuclear Power Plants E. Lee, J. Na, D. Lee, S. Oh, D. Jerng (KHNP) |
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| 9181 : | Risk-Based Assessment of the Allowable Outage Times for the Unit 1 Leningrad Nuclear Power Plant ECCS Components B. Vinnikov (RRC KI), S. Koukhar (LNPP) |
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| 9279 : | Risk-Informed Approach in US-APWR Technical Specifications E. Saji, F. Tanaka, K. Kuroiwa (MHI), K. Kawai (MNES) |
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| 9208 : | SOME ASPECTS ON A GOOD DEPENDABILITY MANAGEMENT FOR A CANDU NPP REACTOR IN ROMANIA G. Vieru (INR) |
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| 9183 : | OSSA – A Second Generation of Severe Accident Management Guidelines E. C. Sauvage, G. Musoyan, V. Ducros (AREVA) |
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|
4-5 Repair and Replacement May 12 (Tue.), 43F-Room 'STAR LIGHT', 14:00 - 15:30 Chair: C. Shih (NTHU), M. Nagase (Hitachi-GENE) |
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| 9397 : | New Maintenance Strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for Safe Long-Term Operation and Ageing Management T. Inagaki, N. Yamashita (TEPCO) |
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| 9029 : | Development of Portable Laser Peening Systems for Nuclear Power Reactors I. Chida, T. Uehara, M. Yoda, H. Miyasaka, H. Kato (Toshiba) |
|||
| * 9327 : | Development of technique to apply induction heating stress improvement to recirculation inlet nozzle M. Ootaka, K. Chiba, K. Nihei (Hitachi-GENE) |
|||
| 9293 : | A guideline for comprehensive evaluation of a licensee's effort to cultivate safety culture M. Makino, Y. Ishii (JNES) |
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|
4-6 Major Component Reliability May 12 (Tue.), 43F-Room 'STAR LIGHT', 15:45 - 17:15 Chair: C. Shih (NTHU), M. Nagase (Hitachi-GENE) |
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| 9388 : | Pilot Valve Instability and Subsequent Damage during Design/Development Testing of a Reactor Circuit Relief Valve for a Pressurised Water Reactor (PWR) Plant, and Development of a Relief Valve Test Facility J. L. Sulley, E. Miller, S. Lockley (Rolls-Royce) |
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| 9008 : | Improvement in Decay Ratio Calculation in LAPUR5 Methodology for BWR Instability H. Lee, T. Yang, C. Shih (NTHU), J. Wang, H. Lin (INER) |
|||
| 9059 : | Size Optimization of Impact Limiter in Transportation Package Based on Dynamic Material Properties W. Choi, K. Bang, J. Lee, K. Seo (KAERI) |
|||
| * 9156 : | Chemical treatment of deposits of junctions “collector – tube” of horizontal steam generators S. N. Alkassem (MPEI) |
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|
4-7 O&M Costs and Operational Experience May 13 (Wed.), 43F-Room 'STAR LIGHT', 09:00 - 10:30 Chair: M. Nagase (Hitachi-GENE), C. Chang (INER) |
||||
| 9414 : | Economical Evaluation for I&C Modernization Approaches in NPPs H. Kang, C. Sung, J. Lee (KHNP) |
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| 9052 : | Measurement Uncertainty Recapture (MUR) Power Uprates Operation at Kuosheng Nuclear Power Station C. Chang (INER), T. Wang (S&L), C. Lin (TPC) |
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| * 9379 : | TEPCO’s Challenges for Occupational Exposure Reduction A. Makihira (TEPCO) |
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| * 9380 : | Application of Zinc Injection to Reduce Radiation Sources at Takahama Unit 4 M. Matsuura, M. Egawa, M. Tukamoto (KEPCO), R. Umehara, T. Nishimura, Y. Shoda (MHI), K. Kasahara (NDC) |
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| Track 5: Plant Safety Assessment and Regulatory Issues (9 sessions) | ||||
|
5-1 Severe Accident LWR/HWR May 11 (Mon.), 47F-Room 'AOZORA', 15:45 - 17:15 Chair: A. Gregoire (IRSN), M. Yoneyama (TEPSYS) |
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| 9001 : | Simulation of First SERENA KROTOS Steam Explosion Experiment M. Uršič, M. Leskovar (JSI) |
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| 9068 : | Interaction of Concretes with Oxide + Metal Corium: The VULCANO VBS Series C. G. Journeau, J. M. Bonnet, L. Ferry, J. F. Haquet, P. Piluso (CEA) |
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| 9083 : | A European Joint Work Plan on Molten Core Concrete Interaction C. G. Journeau (CEA), M. Cranga (IRSN), J. J. Foit (FZK), W. M. Ma (KTH), P. P. Grudev (INRNE) |
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| 9176 : | The Results From the Third High-Pressure Melt Ejection Test Completed in the Molten Fuel Moderator Interaction Facility at Chalk River Laboratories T. Nitheanandan, G. Kyle, B. O’Connor (AECL) |
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| * 9302 : | Heat Removal Capability of Core-catcher with Inclined Cooling Channels Y. Suzuki, M. Tahara, T. Kurita, R. Hamazaki, S. Morooka (Toshiba) |
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| * 9385 : | LIVE Experiments On Melt Behavior In the RPV Lower Head A. Miassoedov, T. Cron, J. Foit, X. Gaus-Liu, A. Palagin, S. Schmidt-Stiefel, T. Wenz (FZK) |
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|
5-2 Source Term May 12 (Tue.), 47F-Room 'AOZORA', 09:00 - 10:30 Chair: T. Nitheanandan (AECL), K. Yanagisawa (JAEA) |
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| 9145 : | Influence of corium oxidation on fission product release from molten pool S. Bechta, E. Krushinov, S. Vitol, S. Kotova, A. Sulatsky, R. Kosarevsky (NITI), V. Gusarov, V. Almyashev (ISC RAS), G. Ducros, C. Journeau (CEA), D. Bottomley (JRC ITU), B. Clément (IRSN), L. Herranz (CIEMAT), S. Guntay (PSI), K. Trambauer (GRS), A. Auvinen (VTT) |
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| 9310 : | PHEBUS FPT2 TEST: OVERVIEW OF FISSION PRODUCTS AND MATERIAL RELEASE AND TRANSPORT IN THE EXPERIMENTAL CIRCUIT A. Gregoire, F. Payot (IRSN) |
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| 9340 : | IODINE CHEMISTRY EFFECT on SOURCE TERM ASSESSMENTS: A MELCOR 1.8.6 YT Study of a PWR Severe Accident Sequence L. Herranz, M. García, B. Otero (CIEMAT) |
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|
5-3 FBR Safety May 12 (Tue.), 47F-Room 'AOZORA', 10:45 - 12:15 Chair: A. Yamaguchi (Osaka Univ.) |
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| 9117 : | Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (1) Overview of Evaluation Methodology Development R. Nakai, T. Suzuki, H. Yamano, H. Seino, H. Ishikawa, K. Kamiyama (JAEA), K. Koyama (MFBR), K. Morita (Kyushu Univ.) |
|||
| 9132 : | Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (2) Identification of Dominant Factors in the Initiating Phase of Unprotected Events I. Sato, H. Yamano, Y. Tobita (JAEA) |
|||
| 9127 : | Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (3) Identification of Dominant Factors in the Transition Phase of Unprotected Events Y. Tobita, H. Yamano, I. Sato (JAEA) |
|||
| 9126 : | Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (4) Identification of Dominant Factors in Core Material Relocation and Heat Removal Phases K. Koyama, Y. Yamada, S. Hayakawa, M. Watanabe, O. Watanabe (MFBR) |
|||
| 9110 : | Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (5) Identification of Dominant Factors in Ex-vessel Accident Sequences S. Ohno, H. Seino, S. Miyahara (JAEA) |
|||
|
5-4 Accident Analysis May 12 (Tue.), 47F-Room 'AOZORA', 14:00 - 15:30 Chair: M. T. Farmer (ANL), T. Sato (Toshiba) |
||||
| 9011 : | Post-Test Analysis of the Quench-13 Bundle Test Including an Ag-In-Cd Absorber Rod J. C. Birchley, T. Haste, B. Jaeckel (PSI), M. Steinbrueck, J. Stuckert (KIT) |
|||
| 9274 : | Assessment of ASTEC-CPA Pool Scrubbing Models against POSEIDON-II and SGTR-ARTIST Data L. E. Herranz, J. Fontanet (CIEMAT) |
|||
| 9007 : | Oxidation of Advanced Zirconium Alloys in Steam at Temperatures 600-1200 °C M. Steinbrueck, M. Grosse (FZK), N. Vér (AEKI) |
|||
| 9040 : | STUDY ON SILICIDE FUEL BEHAVIOR DURING RIA K. Yanagisawa (JAEA) |
|||
|
5-5 Safety Evaluation May 12 (Tue.), 47F-Room 'AOZORA', 15:45 - 17:15 Chair: G. Fiorini (CEA), E. Saji (MHI) |
||||
| 9272 : | Pilot Applications of the Integrated Safety Assessment Methodology G. Rodríguez-Martín, I. Cañamón, C. Queral, A. Expósito, L. Ibáñez, F. J. Elorza (UPM), J. M. Izquierdo, J. Hortal, M. Sánchez-Perea, E. Meléndez, R. Herrero (CSN), J. Gil, I. Fernández, J. Mundina (Indizen Technologies, S.L.), C. Ibáñez, F. Nieto (IIT) |
|||
| * 9332 : | Japanese Standard Method for Safety Evaluation using Best Estimate Code Based on Uncertainty and Scaling Analyses with Statistical Approach S. Mizokami (TEPCO), A. Hotta (TEPSYS), Y. Kudo (GNF-J), T. Yonehara (JANTI), M. Watada (KEPCO), H. Sakaba (MHI) |
|||
| * 9375 : | Activities toward PSA Quality Improvement in Japan S. Imai (TEPCO) |
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| 9488 : | Validation and Applicability of the 3D Core Kinetics and Thermal Hydraulics Coupled Code SPARKLE M. Miyata, M. Maruyama, J. Ogawa, Y. Otake, S. Miyake (MHI), S. Tabuse, H. Tanaka (KEPCO) |
|||
| 9527 : | CIAU Methodology and BEPU Applications A. Petruzzi, F. D'Auria (Univ. of Pisa), A. Kovtonyuk (GRNSPG) |
|||
|
5-6 Risk Information Application May 13 (Wed.), 47F-Room 'AOZORA', 09:30 - 10:30 Chair: K. Kondo (JNES), S. Bilbao y Leon (IAEA) |
||||
| * 9197 : | Study on Practical Application of Risk Informed Inservice Inspection C. Sato, H. Machida, S. Takeda, H. Abe (TEPSYS), K. Miyata, S. Nishino (TEPCO) |
|||
| 9255 : | Shutdown risk monitoring in TEPCO H. Sato, T. Masuda, Y. Denda (TEPCO), M. Yoneyama (TEPSYS), S. Imai, K. Miyata (TEPCO) |
|||
| 9361 : | Upgrade of internal events PSA model using the AESJ Level-1 PSA standard for operating state T. Sato, M. Yoneyama, N. Hirokawa, C. Sato, E. Sato (TEPSYS), S. Tomizawa (TEPCO) |
|||
| 9448 : | A Risk-Informed Perspective on Deterministic Safety Analysis of Nuclear Power Plants P. T. Wan (CNSC) |
|||
|
5-7 Operational Safety & Seismic Safety May 13 (Wed.), 47F-Room 'AOZORA', 10:45 - 12:15 Chair: K. Kondo (JNES) |
||||
| 9412 : | Analysis of Operator Response Strategies To Station Blackout A. Matev (PBMR), J. K. Hohorst (ISS) |
|||
| 9329 : | Reliability and efficiency improvement of wiring work in nuclear power plant M. Ito (Hitachi-GENE) |
|||
| * 9394 : | Approach of Tokyo Electric Power Company in new inspection system K. Furuhashi (TEPCO) |
|||
| * 9374 : | Seismic Margin Analysis for Kashiwazaki Kariwa ABWR Plant Considering the Niigataken Chuetsu-oki Earthquake T. Matsuo, K. Nagasawa, S. Kawamura (TEPCO), T. Ueki, T. Higuchi, I. Sakaki (Toshiba) |
|||
| 9440 : | APPROACH OF SEISMIC UPGRADING IN KASHIWAZAKI-KARIWA NUCLEAR POWER PLANT H. Sato (TEPCO) |
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|
5-8 Safety Design May 13 (Wed.), 47F-Room 'AOZORA', 14:00 - 15:30 Chair: H. Sakaba (MHI), P. T. Wan (CNSC) |
||||
| 9147 : | Design Features to Achieve Defence-In-Depth in Small and Medium Sized Reactors V. V. Kuznetsov (IAEA) |
|||
| 9167 : | Basis for the Safety Approach for Design & Assessment of Generation IV Nuclear Systems G. Fiorini (CEA), T. J. Leahy (INL) |
|||
| 9365 : | Probable Variations of a Passive Safety Containment for a 1700 MWe Class PWR with Passive Safety Systems T. Sato, Y. Fujiki, H. Oikawa (Toshiba), R. P. Ofstun (WEC) |
|||
| 9447 : | Safety Design Philosophy of the ABWR for the Next Generation LWRs T. Sato, M. Akinaga, Y. Kojima (Toshiba) |
|||
|
5-9 RI Diffusion & Dose Evaluation May 13 (Wed.), 47F-Room 'AOZORA', 15:45 - 17:15 Chair: T. Morita (JAPC) |
||||
| 9252 : | NUMERICAL MODEL FOR STACK GAS DIFFUSION IN TERRAIN WITH BUILDINGS - VARIATIONS IN AIR FLOW AND GAS CONCENTRATION WITH THE ADDITIONAL BUILDING NEAR STACK - K. Sada (CRIEPI), S. Komiyama (TEPCO), K. Numata (JAPC), T. Michioka, Y. Ichikawa (CRIEPI) |
|||
| 9376 : | Evaluation of Main Control Room Habitability in Japanese LWR (1) Outline of Evaluation Method and Conditions Y. Fujita, J. Yoneda, R. Fukuda, K. Okabayashi (MHI) |
|||
| 9377 : | Evaluation of Main Control Habitability in Japanese LWR (2) Examination of Atmospheric Dispersion Models by Wind Tunnel Experiments Y. Fujita, R. Fukuda, J. Yoneda, K. Okabayashi (MHI) |
|||
| 9444 : | PLANNING AND ARCHITECTURAL SAFETY CONSIDERATIONS IN DESIGNING NUCLEAR POWER PLANTS A. A. Konsowa (MTC) |
|||
| Track 6: Reactor Physics and Analysis (6 sessions) | ||||
|
6-1 Calculation Method May 11 (Mon.), 3F-Room 'GRACE Room A', 14:00 - 15:30 Chair: T. Yoshida (TCU) |
||||
| 9150 : | Application of the SP3 nodal method with second order source and leakage approximations in axial direction for BWR pin-by-pin core analysis K. Tada, A. Yamamoto, Y. Yamane (Nagoya Univ.), S. Kosaka, G. Hirano (TEPSYS) |
|||
| 9185 : | An Analytical Evaluation for Spatial-Dependent Intra-Pebble Dancoff Factor and Escape Probability S. Kim, H. Kim (HYU), S. Kim (iTRS), J. Noh (KAERI), J. Kim (HYU) |
|||
| 9199 : | A Pin by Pin Microscopic Depletion Scheme using an Homogeneous Core Calculation with Pin-Power Reconstruction F. Hoareau, M. Fliscounakis, D. Couyras, M. Guillo, Y. Pora (EDF R&D) |
|||
| 9246 : | Development of a New Technique for Method of Characteristics with an Approximation on Ray Tracing K. Yamaji, D. Sato, H. Matsumoto (MHI), T. Takeda (Osaka Univ.) |
|||
| 9250 : | Component Analysis of Sodium Void Reactivity of Step Type FBR Cores with Group-wise Monte Carlo Code "GMVP" T. Yokoyama (TNES), Y. Nishiguch (Toshiba) |
|||
| 9401 : | Development of Pin-by-pin Core Analysis Method Using Three-dimensional Direct Response Matrix K. Ishii, T. Hino, T. Mitsuyasu, M. Aoyama (Hitachi) |
|||
|
6-2 Critical Experiment and Analysis May 11 (Mon.), 3F-Room 'GRACE Room A', 15:45 - 17:15 Chair: G. Chang (INL) |
||||
| 9209 : | Deterministic modelling of 100%MOX ABWR lattices with increasing void fraction: validation of the REL2005 code package on the FUBILA Experimental Program P. Blaise, C. Vaglio-gaudard, J. Vidal, J. Ruggieri (CEA) |
|||
| 9210 : | Validation of the REL2005 code package on poisoned PWR type assemblies through the CAMELEON Experimental Program P. Blaise, J. Vidal (CEA) |
|||
| 9251 : | Critical Experiments Simulating The Operating Conditions of PWRs in The Toshiba NCA Facility T. Umano, T. Kikuchi, K. Yoshioka, I. Mitsuhashi, H. Kumanomido, S. Gunji, S. Sugahara, K. Hiraiwa (Toshiba), M. Ouisloumen (WEC) |
|||
| 9290 : | Analysis of Core Physics Experiments on MOX Assemblies Loaded with Gd2O3-UO2 and UO2 Rods T. Yamamoto, Y. Ando, T. Sakai (JNES) |
|||
| 9339 : | Critical Experiments on Minimal-Content Gadolinia for Above-5wt% Enrichment Fuels in Toshiba NCA T. Kikuchi, S. Watanabe, K. Yoshioka, I. Mitsuhashi, H. Kumanomido, S. Sugahara, K. Hiraiwa (Toshiba) |
|||
|
6-3 On-power Reactor Experiment and Analysis May 12 (Tue.), 3F-Room 'GRACE Room A', 09:00 - 10:30 Chair: P. Blaise (CEA) |
||||
| 9081 : | Core modification to improve the irradiation efficiency and increase the core burn-up of the experimental fast reactor Joyo S. Maeda, Y. Ohkawachi, T. Soga, T. Sekine, T. Aoyama (JAEA) |
|||
| * 9113 : | Actinide Decay Heat Error Evaluation on Fast Reactor by Sensitivity Analysis with JENDL-3.3 N. Hagura (TCU), T. Yoshida (Musashi Tech) |
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| 9131 : | Error Sensitivity Analysis of the Doppler Reactivity Coefficient Estimated by a Dynamics Identification Method from Low Power Transient Data of a PWR power plant M. Tsuji, T. Narabayashi, Y. Shimazu (Hokkaido Univ.), Y. Hanayama, Y. Ohoka, M. Yamasaki (NFI) |
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| 9138 : | Improving the AGR Fuel Testing Power Density Profile versus Irradiation-time in the Advanced Test Reactor G. Chang, M. A. Lillo, J. T. Maki, D. A. Petti (INL) |
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| 9243 : | Major upgrade of the reactor dosimetry interpretation methodology used at CEA: architecture description G. Gregoire, C. Destouches, D. Beretz, S. Bourganel (CEA) |
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|
6-4 Nuclear Data and Underlying Physics May 12 (Tue.), 3F-Room 'GRACE Room A', 10:45 - 12:15 Chair: S. Chiba (JAEA) |
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| 9172 : | A Dispersive, Lane-consistent Coupled-channel Optical Model Based on Soft-rotator Theory for Accurate Calculation of Nuclear Reaction Data E. S. Soukhovitski (JIENR), S. Chiba (JAEA), R. Capote (IAEA), J. M. Quesada (Univ. de Sevilla), S. Kunieda (JAEA), G. B. Morogovskij (JIENR) |
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| 9312 : | Nuclear-Charge Polarization at Scission in Fission from Moderately Excited Light-Actinide Nuclei I. Nishinaka (JAEA) |
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| 9400 : | Impact of Up-to-date Evaluated Nuclear Data Files on the Monte-Carlo Analysis Results of Metallic Fueled BFS Critical Assemblies J. Yoo, D. Kim, S. Kim, Y. Kim (KAERI) |
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|
6-5 New Reactor and Cycle Concept May 12 (Tue.), 3F-Room 'GRACE Room A', 14:00 - 15:30 Chair: T. Umano (Toshiba) |
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| 9190 : | Preliminary Core Design of IRIS-50 B. Petrovic (Georgia Tech), F. Franceschini (WEC) |
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| 9233 : | Reactor Physical Experimental Program EROS in the frame of the Molten Salt applying Reactor Concepts Development M. J. Hron, J. Kyncl, M. Mikisek (NRI) |
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| 9341 : | Study of the Burnup Behavior, Safety Characteristics and Transmutation Performance of the LWRs with Innovative Fuel Concepts R. Nabbi, H. Allelein, W. V. Lensa, O. Schitthelm (FZJ) |
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| * 9416 : | Application Study of NFI 9x9 fuel for extended cycle operation of BWR up to 24months T. Miyaji, Y. Aoki, K. Oguchi (NFI) |
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|
6-6 Novel Technology May 12 (Tue.), 3F-Room 'GRACE Room A', 15:45 - 17:15 Chair: B. Petrovic (Georgia Tech) |
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| 9085 : | Research and development of the software for visualizing nuclear reactor and neutronics analysis. S. Okui, H. Sekimoto (TIT) |
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| * 9180 : | THEORETICAL HYPOTHESIS OF A DOUBLE BARRIER REGARDING THE D-D INTERACTION IN A PD LATTICE F. Frisone (Univ. of Catania) |
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| 9015 : | Analysis of Spent Fuel Assay With a Lead Slowing Down Spectrometer V. Gavron (LANL), L. E. Smith (PNNL) |
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| 9521 : | All Heavy Metals Closed-Cycle Analysis on Water-Cooled Reactors of Uranium and Thorium Fuel Cycle Systems S. Permana (TIT), A. Waris (ITB), N. Takaki (Tokai Univ.), H. Sekimoto (TIT) |
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| Track 7: Thermal Hydraulics Analysis and Testing (12 sessions) | ||||
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7-1 Advances in Two-phase Flow and Heat Transfer-I May 11 (Mon.), 43F-Room 'MOON LIGHT', 14:00 - 15:30 Chair: K. Yoneda (CRIEPI), N. Aksan (PSI) |
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| 9352 : | Implementation of Non-Drag Interfacial Forces into the CUPID Code I. Park, H. Cho, J. Kim, H. Yoon, J. Jeong (KAERI) |
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| 9334 : | INTERFACIAL AREA TRANSPORT OF VERTICAL UPWARD AIR-WATER TWO-PHASE FLOW IN AN ANNULUS AT ELEVATED PRESSURES B. Ozar (PU), D. Euh (KAERI), T. Hibiki, M. Ishii (PU) |
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| 9491 : | Entrainment in Vertical Annular Two-Phase Flow P. Sawant, M. Ishii (PU), M. Mori (TEPCO) |
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| * 9423 : | Experimental Study on Bubble Departure and Lift-off diameter in Subcooled Pool Boiling Near Vertically Heated Wall Y. Cho, S. Yoon, G. Park (SNU) |
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|
7-2 Advances in Two-phase Flow and Heat Transfer-II May 11 (Mon.), 43F-Room 'MOON LIGHT', 15:45 - 17:15 Chair: Y. Nishi (CRIEPI), H. Park (KAERI) |
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| 9114 : | The Effective Convectivity Model for Simulation of Molten Metal Layer Heat Transfer in a Boiling Water Reactor Lower Head T. C. Tran, P. Kudinov (KTH) |
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| * 9463 : | Large Eddy Simulation of the Flow in a T-junction E. Merzari (TIT), E. Baglietto (CD-Adapco), H. Ninokata (TIT) |
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| 9003 : | Experimental and Theoretical Study of Steam Condensation Induced Water Hammer Phenomena I. F. Barna, G. Baranyai, G. Ézsöl (AEKI) |
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| * 9462 : | Numerical Simulation of the Flow in a Natural Circulation Loop with Nanofluids and Differential Heating E. Merzari, I. Bang, H. Ninokata (TIT) |
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|
7-3 CFD Applications to Water, Liquid Metal and Gas Reactors-I May 12 (Tue.), 43F-Room 'MOON LIGHT', 09:00 - 10:30 Chair: K. Takase (JAEA), A. Kovtonyuk (Univ. of Pisa.) |
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| 9142 : | Safety Evaluation of the Large BWR Assembly With Small Pins A. Karahan, Y. Kimura, K. Kito, P. Hejzlar, M. S. Kazimi (MIT) |
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| 9136 : | The Limiting Events Transient Analysis by RETRAN02 and VIPRE for an ABWR C. Tsai, C. Shih (NTHU), J. Wang, H. Lin, J. Jin (INER), S. Cheng (Taiwan Power Co.) |
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| 9051 : | Validation Study of FLUENT for the Application of Dry-Storage System Thermal Analysis Y. Tseng, J. Wang (INER), Y. Cheng, C. Shih (NTHU) |
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| 9164 : | CFD Modeling of Pool Swell During Large Break LOCA J. Yan, F. Bolger, G. Li (GE-Hitachi) |
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|
7-4 CFD Applications to Water, Liquid Metal and Gas Reactors-II May 12 (Tue.), 43F-Room 'MOON LIGHT', 10:45 - 12:15 Chair: M. Murase (INSS), A. A. Batta (FZK) |
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| 9285 : | Application of U-RANS to Elbow Pipe Flow with Small Curvature Radius under High Reynolds Number Condition M. Tanaka, H. Ohshima, H. Yamano, K. Aizawa (JAEA), T. Fujisaki (NDD) |
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| 9096 : | PRESSURE LOSS PREDICTIONS IN CFD SIMULATIONS OF WIRE-WRAPPED SFR FUEL ASSEMBLIES J. G. Smith, A. Tokuhiro (Univ. of Idaho), W. D. Pointer, P. F. Fischer (ANL) |
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| 9311 : | Three Dimensional Conjugated Heat Transfer Analysis in Sodium Fast Reactor Wire-wrapped Fuel Assembly C. Peniguel, J. Juhel, I. Rupp (EDF), S. Rolfo (Univ. of Manchester), N. Gervais, M. Guillaud (INCKA) |
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| * 9382 : | High Resolution Calculation of Heat Transfer in HTGR Reactor Cavity Cooling Systems A. Charmeau, B. Ahmed, A. Wysocki, H. Wei, M. P. Rose, B. W. Cunningham, S. Anghaie (Univ. of Florida) |
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| 9445 : | Fluid Flow and Heat Transfer Analysis of the HTR-10 Reactor Cavity Cooling System during Heat-up Accidents H. Wei, M. Rose, A. Charmeau, B. Ahmed, S. Anghaie (Univ. of Florida) |
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|
7-5 CFD Applications to Water, Liquid Metal and Gas Reactors-III May 12 (Tue.), 43F-Room 'MOON LIGHT', 14:00 - 15:30 Chair: T. Misawa (JAEA), S. Leyer (AREVA) |
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| * 9158 : | Full scale quasi steady state component tests of the SWR 1000 Emergency Condenser at the INKA test facility S. Leyer, F. Maisberger, B. Schaub, W. Brettschuh, M. Doll, M. Wich, H. Schäfer (AREVA), A. Manera, H. M. Prasser (PSI) |
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| 9159 : | Full scale steady state component tests of the SWR 1000 Fuel Pool Cooler at the INKA test facility S. Leyer, F. Maisberger, B. Schaub, W. Brettschuh, M. Doll, T. Wagner, M. Wich, H. Schäfer, V. Fischer, D. Walter, R. Walterskötter (AREVA) |
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| 9292 : | Numerical simulation of complex multi-dimensional two-phase flows in nuclear power plant coolant circuits by means of the best-estimate thermal hydraulic code BAGIRA V. E. Kroshilin, A. E. Kroshilin, S. D. Kalinichenko, A. V. Smirnov (VNIIAES) |
|||
| 9330 : | CFD Simulation of a Turbulent Flow along a Row of Confined Cylinders M. Kim, W. Lee (KAERI) |
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|
7-6 CFD Applications to Water, Liquid Metal and Gas Reactors-IV May 12 (Tue.), 43F-Room 'MOON LIGHT', 15:45 - 17:15 Chair: M. Tanaka (JAEA), J. G. Smith (Univ. of Idaho) |
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| 9193 : | Evaluation of Thermal-Hydraulic Behaviors in Loss-of-RHR Event during Mid-loop Operation M. Murase, H. Nagumo, N. Minami, Y. Utanohara, I. Kinoshita (INSS) |
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| 9153 : | DRACCAR, a new 3D-thermal mechanical computer code to simulate LOCA transient on Nuclear Power Plants : status of the development and the validation G. Repetto, F. Jacq, F. Lamare, J. Ricaud, F. Barré (IRSN) |
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| 9378 : | CATHARE SIMULATION OF TRANSIENTS FOR THE 2400 MW GAS FAST REACTOR CONCEPT F. Bentivoglio, A. Messie (CEA) |
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| 9509 : | A Nusselt number correlation of the Printed Circuit Heat Exchanger proposed by CFD simulations I. Kim, H. No, J. Lee, B. Jeon (KAIST) |
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|
7-7 CFD Code and Validation May 13 (Wed.), 43F-Room 'MOON LIGHT', 09:00 - 10:30 Chair: F. Inada (CRIEPI), G. Bandini (ENEA) |
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| 9177 : | VALIDATION OF TRACE USING THE VOID FRACTION TESTS OF THE NUPEC BFBT FACILTITY M. Thieme (KIT), W. Tietsch (WEG), R. Macian (TUM), V. H. Sánchez Espinoza (KIT) |
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| 9010 : | TRACE Analysis of Lumgmen ABWR for Loss of Feedwater Flow Event J. Wang, H. Lin (INER), W. Wang, S. Yang, C. Shih (NTHU) |
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| 9247 : | A Separate Effect Test on the Core Cooling Behavior under a Low Reflooding Rate Condition by using the ATLAS H. Park, K. Choi, S. Cho, K. Kang, D. Kim, N. Choi, Y. Kim, W. Baek (KAERI) |
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|
7-8 Thermal Hydraulics of LMFR Systems May 13 (Wed.), 43F-Room 'MOON LIGHT', 10:45 - 12:15 Chair: T. Sakai (JAEA), J. Cha (KAERI) |
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| * 9239 : | COMPASS Code Development and Validation: A Muti-Physics Analysis of Core Disruptive Accidents in Sodium-Cooled Fast Reactors Using Particle Method S. Koshizuka, J. Liu (Univ. of Tokyo), K. Morita, T. Arima, S. Zhang (Kyushu Univ.), Y. Tobita, H. Yamano (JAEA), T. Ito (Toyohashi Univ.), M. Naitoh, N. Shirakawa, S. Hosoda, Y. Uehara (IAE), Y. Yamamoto, H. Kozakai, M. Himi, E. Hirano, S. Shimizu, M. Oue (Japan Systems Corp.) |
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| 9507 : | Comparison of thermo-hydraulic analysis with measurements for HELIOS - the scaled integral test loop for PEACER J. Cho, J. Lim, J. Kim, I. Hwang (SNU) |
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| 9436 : | Analysis and Testing of W-DHR System for Decay Heat Removal in the Lead-Cooled ELSY Reactor G. Bandini, P. Meloni, M. Polidori, P. Gaggini, V. Labanti, M. Tarantino (ENEA), L. Cinotti, L. Presciuttini (DEL) |
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| 9439 : | Experimental and Numerical Investigation of Turbulent Liquid Metal Heat Transfer along a Heated Rod in Annular Cavity A. A. Batta, J. Zeininger, R. Stieglitz (FZK) |
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|
7-9 Thermal Hydraulics of SCWR Systems-I May 13 (Wed.), 43F-Room 'MOON LIGHT', 14:00 - 15:30 Chair: Y. Seki (JAEA), S. Bilbao y Leon (IAEA) |
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| 9368 : | Experimental Study for Research and Development of a Super Fast Reactor (1) Critical Heat Flux in the Near-critical Pressure Region H. Mori, M. Ohno, Y. Hamamoto (Kyushu Univ.) |
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| 9369 : | Experimental Study for Research and Development of a Super Fast Reactor (2) Oscillatory Condensation of High Temperature Vapor Directly Discharged into Sub-cooled Liquid Pool H. Mori, Y. Hamamoto, M. Ohno (Kyushu Univ.) |
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| 9475 : | Mechanistic Multidimensional Analysis of Heat Transfer in Fluids at Supercritical Pressures M. Z. Podowski, T. Gallaway, S. P. Antal (RPI) |
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| 9134 : | Assessment of Heat Transfer Correlations for Supercritical Water in the Frame of Best-Estimate Code Validation W. Jaeger (FZK/INR), V. H. Sánchez Espinoza (FZK/IRS), N. Schneider (Univ. of Wiesbaden), A. Hurtado (Tech. Univ. of Dresden) |
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|
7-10 Thermal Hydraulics of SCWR Systems-II May 13 (Wed.), 43F-Room 'MOON LIGHT', 15:45 - 17:15 Chair: H. Mori (Kyushu Univ.), W. Jaeger (FZK/INR) |
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| * 9464 : | Heat Transfer in a Seven-Rod Test Bundle with Supercritical Pressure Water -(1): Experiments K. Ezato, Y. Seki, M. Dairaku, S. Suzuki, M. Enoeda, M. Akiba (JAEA), H. Mori (Kyushu Univ.), H. Oka (Univ. of Tokyo) |
|||
| * 9487 : | Heat Transfer in a Seven-Rod Test Bundle with Supercritical Pressure Water (2) Numerical Simulation T. Misawa, T. Nakatsuka, H. Yoshida, K. Takase (JAEA) |
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| 9482 : | IAEA Coordinated Research Programme on Heat Transfer Behavior and Thermo-Hydraulics Code Testing for Super Critical Water Cooled Reactors S. Bilbao y Leon (IAEA), N. Aksan (PSI) |
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|
7-11 Heat Transfer in Fuel Pin Bundle May 13 (Wed.), 43F-Room 'STAR LIGHT', 10:45 - 12:15 Chair: M. Takahashi (TIT), M. T. Farmer (ANL) |
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| 9337 : | Computational Fluid Dynamics Analysis for K24B Cask Design with Burnup Credit S. Yoon (SNU), D. Lee, J. Park (KONES), G. Park (SNU) |
|||
| 9216 : | Development of the Cooling Technology on TRU Fuel Pin Bundle during Fuel Fabrication Process (4) Steady state cooling test of full mock up fuel pin bundle K. Itoh, K. Ikeda (NDC), K. Hishida (Keio Univ.), A. Yamaguchi, T. Takata, Y. Manabe (Osaka Univ.) |
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| * 9207 : | Development of the Cooling Technology on TRU Fuel Pin Bundle during Fuel Fabrication Process(5)Development of heat transfer correlation for sub-channel analysis tool Y. Manabe, T. Takata, A. Yamaguchi (Osaka Univ.), K. Hishida (Keio Univ.), K. Itoh, K. Ikeda (NDC) |
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| 9163 : | Design Optimization of A T Mixing Vane in Nuclear Fuel Assembly S. Jung, M. Moon, K. Kim (Inha Univ.) |
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| 9093 : | Assessment of New Modeling in RELAP/SCDAPSIM Using Experimental Results from the Quench Program J. Hohorst, L. Siefken, C. Allison (ISS) |
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|
7-12 System Analysis and Assessment May 13 (Wed.), 43F-Room 'STAR LIGHT', 14:00 - 15:30 Chair: Y. Kitajima (TOSHIBA), I. Kinoshita (CRIEPI) |
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| 9372 : | Computational Investigation of Pressure Fluctuations in BWR Main Steam Line R. Morita, F. Inada (CRIEPI), S. Takahashi (Hitachi), K. Yoshikawa (Hitachi-GENE) |
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| 9030 : | Characteristics of Fluctuating Pressure Generating in BWR Main Steam Lines S. Takahashi, K. Okuyama, A. Tamura, K. Nishida, M. Ohtsuka (Hitachi), M. Tsubaki, Y. Mabuchi, K. Yoshikawa (Hitachi-GENE), F. Inada, R. Morita (CRIEPI) |
|||
| 9054 : | Design Improvements of Passive Flow Controlling Safety Injection Tank I. Chu, T. Kwon, C. Song (KAERI) |
|||
| 9098 : | Containment safety: on the analysis of a light gas stratification break-down by a water spray J. Malet (IRSN), J. Vizet (Bertin Services), E. Porcheron, J. Vendel (IRSN) |
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| 9424 : | A study of small nuclear power plant system for district heating M. Imamura, K. Sato, T. Narabayashi, Y. Shimazu, M. Tsuji (Hokkaido Univ.) |
|||
| Track 8: Fuel Cycle and Waste Management (9 sessions) | ||||
|
8-1 Waste Management (1) May 11 (Mon.), 4F-Room 'NATSUME', 14:00 - 15:30 Chair: W. D. Downing (SwRI), T. Washiya (JAEA) |
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| 9006 : | The Importance of Independent Research and Evaluation in Assessing Nuclear Fuel Cycle and Waste Management Facility Safety W. D. Downing, W. C. Patrick, B. Sagar (SwRI) |
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| 9465 : | Current Status on Advanced Aqueous Reprocessing Process (NEXT) in FaCT Project T. Washiya, M. Myochin, T. Koyama (JAEA) |
|||
| 9415 : | Need for Asian Regional Spent Fuel Recycle Center (ARRC) O. Yamamura (JAEA) |
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|
8-2 Waste Management (2) May 11 (Mon.), 4F-Room 'NATSUME', 15:45 - 17:15 Chair: W. D. Downing (SwRI) |
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| 9411 : | DEVELOPMENT OF NEW TREATMENT PROCESS FOR LOW LEVEL RADIOACTIVE WASTE AT TOKAI REPROCESSING PLANT K. Horiguchi, A. Sugaya, Y. Saito, K. Tanaka, S. Akutsu, T. Hirata (JAEA) |
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| 9144 : | Development of Biological Treatment of High Concentration Sodium Nitrate Waste Liquid N. Ogawa, K. Kuroda (MHI), Y. Kawato, Y. Meguro, K. Takahashi (JAEA) |
|||
| 9301 : | Perfomance of cement solidification with barium for high activity liquid waste including sulphate T. Waki, M. Yamada, Y. Horikawa (KEPCO), M. Kaneko, M. Saso, Y. Haruguchi, Y. Yamashita, H. Sakai (Toshiba) |
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|
8-3 Qualification and Monitoring May 12 (Tue.), 4F-Room 'NATSUME', 09:00 - 10:30 Chair: D. Tsumune (CRIEPI) |
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| * 9518 : | Monitoring of Released Radioactive Gaseous and Liquid Effluent at Rokkasho Reprocessing Plant M. Oka, S. Keta, S. Nagai, M. Kano, N. Ishihara, T. Moriyama, K. Ogaki, K. Noda (JNFL) |
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| 9429 : | Environmental radioactivity monitoring around the Rokkasho Reprocessing Plant K. Sasaki, H. Hareyama, M. Takeishi (JNFL) |
|||
| 9492 : | Impact assessment at the submergence of radioactive materials during sea transport D. Tsumune, T. Tsubono, T. Saegusa, C. Ito (CRIEPI) |
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| 9323 : | QUALIFICATION TESTING FACILITY FOR PACKAGES TO BE USED FOR TRANSPORT AND STORAGE OF RADIOACTIVE MATERIALS G. Vieru (INR) |
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|
8-4 Fuel Fabrication Process May 12 (Tue.), 4F-Room 'NATSUME', 10:45 - 12:15 Chair: M. A. Pouchon (PSI) |
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| 9457 : | Outline of J-MOX Program and Safety Measures T. Sato, Y. Yamaji, A. Oe, M. Fujita (JNFL) |
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| 9494 : | Internal Gelation at PSI: The past and the future M. A. Pouchon, F. Ingold (PSI) |
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| 9461 : | Confirmation Test on J-MOX Powder Process H. Ota, S. Osaka, I. Kurita (JNFL) |
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|
8-5 Material Property May 12 (Tue.), 4F-Room 'NATSUME', 14:00 - 15:30 Chair: Y. Rugama (OECD NEA), J. Kim (KAERI) |
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| 9314 : | Radiation Stability of Proton Irradiated Zirconium Carbide Y. Yang, C. A. Dickerson, T. R. Allen (UW) |
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| 9451 : | Melting Temperatures of Oxide Fuel for Fast Reactor M. Kato (JAEA) |
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| 9057 : | OECD/NEA EXPERT GROUP ON ASSAY DATA OF SPENT NUCLEAR FUEL Y. Rugama (OECD NEA), K. Suyama (JAEA), I. Gauld (ORNL) |
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| 9095 : | Performance of the Diffusion Barrier in the Metallic fuel in Sodium-cooled Fast Reactor J. Kim, H. Ryu, S. Yang, B. Lee, S. Oh, C. Lee, D. Hahn (KAERI) |
|||
| 9305 : | Study on the improved evaluation of radioactivity of activated control rods in PWR A. Sakashita (MHI), T. Waki, M. Yamada, Y. Horikawa (KEPCO), Y. Miyake (MHI) |
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|
8-6 Fuel Cycle (1) May 12 (Tue.), 4F-Room 'NATSUME', 15:45 - 17:15 Chair: M. Yamasaki (NFI) |
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| 9319 : | Progress of Criticality Experiments and Nuclear Design Studies on Erbia-Bearing Super High Burnup Fuel M. Yamasaki, T. Kuroishi (NFI), T. Takeda (Osaka Univ.), A. Yamamoto (Nagoya Univ.), H. Unesaki (Kyoto Univ.), M. Mori (NEL), T. Sano (Kyoto Univ.) |
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| 9171 : | Methodology for investigating the applicability of thorium based fuels in existing BWRs K. Insulander Björk, V. Fhager (Thor Energy), C. Demazière (Chalmers Univ.) |
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| 9170 : | Comparison of thorium-based fuels with different fissile components in existing BWRs K. Insulander Björk, V. Fhager (Thor Energy), C. Demazière (Chalmers Univ.) |
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| 9517 : | Breeding and Plutonium Characterization analysis on Actinides Closed Water-Cooled Thorium Reactor S. Permana (TIT), N. Takaki (Tokai Univ.), H. Sekimoto (TIT) |
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|
8-7 Fuel Cycle (2) May 13 (Wed.), 4F-Room 'NATSUME', 09:00 - 10:30 Chair: J. Krepel (PSI) |
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| 9227 : | EFIT fuel cycle analysis with the EQL3D procedure J. Krepel (PSI), M. Sarotto (ENEA), K. Mikityuk (PSI), C. Artioli (ENEA) |
|||
| 9526 : | Core Performance and Plutonium Production of Small Long Life Fast Reactor using Doping Actinides S. Permana (TIT), Z. Suud (ITB) |
|||
| * 9297 : | Enhancing the uranium utilization rate in LWRs: a step toward a sustainable nuclear energy M. Delpech (CEA), D. Greneche (AREVA) |
|||
| 9260 : | Fuel Cycle Aspects of Molten Salt Reactor System J. Uhlir (NRI) |
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|
8-8 Scenario Analysis (1) May 13 (Wed.), 4F-Room 'NATSUME', 10:45 - 12:15 Chair: T. Fukasawa (Hitachi-GENE) |
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| * 9413 : | Parameters’ influence estimation on Puf Supply & Demand in transitional period from LWR to FBR in Japan H. Kobayashi, H. Ohta, T. Inoue (CRIEPI) |
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| 9513 : | Flexible Fuel Cycle System for the Transition from LWR to FBR T. Fukasawa, J. Yamashita, K. Hoshino (Hitachi-GENE), A. Sasahir (Hitachi), T. Inoue (CRIEPI), K. Minato (JAEA), S. Sato (Hokkaido Univ.) |
|||
| 9148 : | Feasibility Study of Recycle Material Storage Facility in the Flexible Fuel Cycle System during Transition from LWR Cycle to FBR Cycle K. Fujimura, A. Sasahira (Hitachi), T. Fukasawa, J. Yamashita, K. Hoshino (Hitachi-GENE), Y. Shimazu, K. Sugiyama (Hokkaido Univ.) |
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|
8-9 Scenario Analysis (2) May 13 (Wed.), 4F-Room 'NATSUME', 14:00 - 15:30 Chair: M. Kawashima (TNES) |
||||
| 9218 : | Analysis of Fast Reactor Scenario with Different Conversion Ratio C. Jeong, W. Ko (KAERI) |
|||
| 9222 : | Reduction of Nuclear Waste Burden from LWR by Deployment of the SCNES M. Kawashima (TNES), K. Arie, J. Watanabe, K. Mori, K. Kubota (Toshiba), Y. Nakayama, R. Nakazono, Y. Kuroda (JAPC), Y. Fuji-ie (NSF) |
|||
| * 9421 : | Toward A Sustainable Energy Supply with Reduced Environmental Burden: Development of Metal Fuel Fast Reactor Cycle T. Koyama, H. Kobayashi, K. Kinoshita (CRIEPI) |
|||
| Track 9: Materials and Structural Issues (14 sessions) | ||||
|
9-1 LWR Reactor Design and Irradiation May 11 (Mon.), 47F-Room 'AKEBONO', 14:00 - 15:30 Chair: R. Srinivasan (AREVA) |
||||
| 9191 : | Material Property Changes of Stainless Steel under PWR Irradiation K. Fukuya, H. Nishioka, K. Nishioka, T. Miura (INSS), T. Torimaru (NFD) |
|||
| 9422 : | INFLUENCE OF ANNEALING ON GRAIN BOUNDARY SEGREGATION OF NEUTRON IRRADIATED TYPE 316L STAINLESS STEEL Y. Ishiyama, M. Kodama (NFD) |
|||
| 9425 : | Effect of Neutron Flux on IASCC Susceptibility in Type 304 Stainless Steel M. Kodama, T. Torimaru (NFD) |
|||
|
9-2 LWR Fatigue May 11 (Mon.), 47F-Room 'AKEBONO', 15:45 - 17:15 Chair: W. Ryu (KAERI) |
||||
| * 9086 : | Cyclic response and dislocation structures evolution of TP 347 piping stainless steel during thermomechanical and low cycle fatigue loading M. Ramesh, H. Leber (PSI), C. Solenthaler, M. Diener, R. Spolenak (ETHZ) |
|||
| 9403 : | Low Cycle Fatigue Behaviors of Elbow Pipe with Local Wall Thinning K. Takahashi, K. Ando (Yokohama National Univ.), Y. Urabe (JANTI), S. Watanabe (Yokohama National Univ.), M. Hisatsune, A. Hidaka (Hitachi-GENE) |
|||
| 9407 : | Environmental Fatigue Behaviors of Wrought and Cast Stainless Steels in 310oC Deoxygenated Water P. Cho, H. Jang (KAIST), I. Jeong (KEPRI), J. Lee (NETEC), C. Jang (KAIST) |
|||
| * 9431 : | Intergranular Cracking Susceptibility of Alloy 152 in Low Temperature Water with Hydrogen Y. Nomura, K. Tsutsumi (MHI), H. Kanasaki, S. Asada (NHI) |
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|
9-3 LWR Corrosion May 12 (Tue.), 47F-Room 'AKEBONO', 09:00 - 10:30 Chair: T. W. Knight (USC) |
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| 9511 : | Crevice Corrosion Control for Stainless Steel Using Radiation-Induced Surface Activation T. Kato, T. Hazuku, S. Motoda, T. Takamasa, M. Hishida, T. Kumata (TUMSAT), H. Abe (Univ. of Tokyo), M. Furuya (CRIEPI) |
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| 9396 : | Inspection of Piping Wall Loss with Flow Accelerated Corrosion Accelerated Simulation Test K. Ryu, J. Kim, S. Lee, I. Hwang (SNU), N. Lee (KINAC) |
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| 9495 : | STUDY ON PIPE WASTAGE MECHANISM BY LIQUID DROPLET IMPINGEMENT EROSION Y. Higashi, T. Narabayashi, Y. Shimazu, M. Tsuiji (Hokkaido Univ.), S. Ohmori, M. Mori, K. Tezuka (TEPCO) |
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9-4 LWR SCC/Residual Stress May 12 (Tue.), 47F-Room 'AKEBONO', 10:45 - 12:15 Chair: T. Kido (NDC) |
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| 9399 : | Effect of Surface Treatments on Stress Corrosion Cracking Susceptibility of Nickel Base Alloys M. Iwanami, J. Kaneda, H. Tamako (Hitachi-GENE), H. Hato (Hitachi), S. Takamoto (BHK) |
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| * 9430 : | SCC Growth Rate of Cold Worked Austenitic Stainless Steel in PWR Y. Nomura, T. Kobayashi (MHI) |
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| * 9486 : | Residual Stress Measurement and Analysis of Dissimilar Metal Surge Line Nozzle N. Ogawa, I. Muroya, Y. Iwamoto, T. Ohta (MHI), K. Nakacho (Osaka Univ.), K. Ogawa (JNES) |
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9-5 LWR Welding/Bolting May 12 (Tue.), 47F-Room 'AKEBONO', 14:00 - 15:30 Chair: K. Itoh (NDC) |
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| 9024 : | Metallurgical and Mechanical investigation into the Simulated Weld HAZs of SA508 Gr.4N Reactor Pressure Vessel Steel M. Kim, B. Lee (KAERI) |
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| 9075 : | Underwater Laser Beam Welding of Alloy 690 T. Hino, M. Tamura, W. Kono, S. Kawano, M. Yoda (Toshiba) |
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| 9044 : | Estimation on Clamping Force of High Strength Bolt by Temperature Parameter H. Nah, K. Kim, H. Lee (KEPCO), W. Kim (Kongju National Univ.) |
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| 9103 : | The Evaluation on Clamping force of High Strength Bolts by Length Parameter K. Kim, H. Nah, H. Lee (KEPRI), K. Lee (CNU) |
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9-6 LWR Component May 12 (Tue.), 47F-Room 'AKEBONO', 15:45 - 17:15 Chair: R. Srinivasan (AREVA), K. Itoh (NDC) |
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| 9192 : | A New Seismic Damage Analysis Method for Cylindrical Liquid Storage Tanks in Nuclear Power Plants A. Maekawa (INSS) |
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| 9256 : | A Structural Design of Nuclear Power Plant Using Stiffened Steel Plate Concrete Structure I. Moon (KOPEC), T. Mun (KHNP), S. Kim (KOPEC), K. Kim, W. Sun (KHNP) |
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| 9453 : | Effect of microstructure on ion-irradiation-induced hardening in A533B model alloys at 563K K. Murakami, H. Abe, T. Iwai, S. Tamura, Y. Katano, T. Iwata, T. Nishida, N. Sekimura (Univ. of Tokyo) |
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| 9484 : | Study on Seismic Design Margin based upon Inelastic Shaking Test of the Piping and Support System T. Ishiguro (KEPCO), K. Eto (Kyuden), K. Ikeda (Shikoku Electric Power Co., INC), T. Yoshii (Hokkaido Univ.), M. Kondo (JAPC), K. Tai (MHI) |
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| 9389 : | Hot Isostatically Pressed (HIPed) Thick Walled Component for a Pressurised Water Reactor (PWR) Application J. L. Sulley, I. Hookham, B. Burdett, K. Bridger (Rolls-Royce) |
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9-7 Super ODS (1) May 13 (Wed.), 47F-Room 'AKEBONO', 09:00 - 10:30 Chair: F. Balbaud-Célérier (CEA) |
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| 9220 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 1) Introduction and alloy design A. Kimura, R. Kasada, N. Iwata, H. Kishimoto, C. Zhang, P. Dou, J. Isselin, N. Muthkumar, J. Lee (Kyoto Univ.), T. Okuda (KOBELCO), M. Inoue (JAEA), S. Ukai, S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.), F. Abe (NIMS) |
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| 9306 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 2) Effect of minor alloying elements S. Ohnuki, N. Hashimoto, S. Ukai (Hokkaido Univ.), A. Kimura (Kyoto Univ.), M. Inoue, T. Kaito (JAEA), T. Fujiwara (Nagoya Univ.), T. Okuda (COBELCO), F. Abe (NIMS) |
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| 9229 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 3) Development of high-performance attrition type ball mill T. Okuda, M. Fujiwara, T. Nakai, K. Shibata (KRI), A. Kimura (Kyoto Univ.), M. Inoue (JAEA), S. Ukai, S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.), F. Abe (NIMS) |
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| 9221 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 4) Mechanical Properties at Elevated Temperatures T. Furukawa, S. Ohtsuka, M. Inoue (JAEA), T. Okuda (KOBELCO), F. Abe (NIMS), S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.), A. Kimura (Kyoto Univ.) |
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9-8 Super ODS (2) May 13 (Wed.), 47F-Room 'AKEBONO', 10:45 - 12:15 Chair: F. Balbaud-Célérier (CEA) |
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| 9072 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 5) Mechanical properties and microstructure R. Kasada, C. Zhang, P. Dou, J. Isselin, S. Lee, A. Kimura (Kyoto Univ.), M. Inoue (JAEA), S. Ukai, S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.), T. Okuda (KOBELCO), F. Abe (NIMS) |
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| 9223 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 6) Corrosion behavior in SCPW A. Kimura, J. Lee, R. Kasada, N. Iwata, H. Kishimoto, C. Zhang, J. Isselin, P. Dou, N. Muthkumar (Kyoto Univ.), T. Okuda (KOBELCO), M. Inoue (JAEA), S. Ukai, S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.), F. Abe (NIMS) |
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| 9308 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 7) Corrosion Behavior and Mechanism in LBE H. Sano, T. Fujisawa (Nagoya Univ.), A. Kimura (Kyoto Univ.), M. Inoue (JAEA), S. Ukai, S. Ohnuki (Hokkaido Univ.), T. Okuda (KOBELCO), F. Abe (NIMS) |
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| 9219 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 8) Ion Irradiation Effects at Elevated Temperatures H. Kishimoto (Muroran-IT), R. Kasada, A. Kimura (Kyoto Univ.), M. Inoue (JAEA), T. Okuda (KOBELCO), F. Abe (NIMS), S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.) |
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| 9307 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 9) Damage structure evolution under electron-irradiation S. Ohnuki, N. Hashimoto, S. Ukai (Hokkaido Univ.), A. Kimura (Kyoto Univ.), M. Inoue, T. Kaito (JAEA), T. Fujiwara (Nagoya Univ.), T. Okuda (COBELCO), F. Abe (NIMS) |
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| 9232 : | Super ODS Steels R&D for Fuel Cladding of Next Generation Nuclear Systems 10) Cladding tube manufacturing and summary S. Ukai (Hokkaido Univ.), A. Kimura (Kyoto Univ.), M. Inoue, T. Kaito (JAEA), S. Ohnuki (Hokkaido Univ.), T. Fujisawa (Nagoya Univ.), T. Okuda (KRI), F. Abe (NIMS) |
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9-9 LWR Management May 13 (Wed.), 47F-Room 'AKEBONO', 14:00 - 15:30 Chair: R. Srinivasan (AREVA) |
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| 9168 : | Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology T. R. Allen, M. C. Thelen, M. K. Meyer, J. A. Foster, F. M. Marshall, J. B. Benson (ATR NSUF) |
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| 9325 : | LWR aging management using a proactive approach to control materials degradation L. J. Bond, S. R. Doctor, S. E. Cumblidge, S. M. Bruemmer, W. B. Taylor (PNNL), A. B. Hull, S. N. Malik (US NRC) |
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| 9395 : | A Probabilistic EAC Management of Ni-base alloy in PWR T. Lee, I. Hwang (SNU) |
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9-10 SCWR and Future Applications May 13 (Wed.), 47F-Room 'AKEBONO', 15:45 - 17:15 Chair: K. Itoh (NDC) |
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| 9289 : | Evaluation of weight loss of Stainless Steels in Supercritical Water Y. Maruno, J. Kaneda, S. Kasahara (Hitachi), N. Saito (Toshiba), T. Shikama, H. Matsui (Tohoku Univ.) |
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| 9428 : | Thermal and Irradiation Effects on High Temperature Mechanical Properties of Materials for SCWR Fuel Claddings F. Kano, Y. Tsuchiya, K. Oka, N. Saito, S. Mimura (Toshiba), S. Kasahara (Hitachi), J. Kaneda (Hitachi-GENE), H. Matsui (Kyoto Univ.), T. Shikama, M. Narui (Tohoku Univ.), Y. Oka (Univ. of Tokyo) |
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| 9456 : | Corrosion properties of modified PNC1520 austenitic stainless steel in supercritical water as a fuel cladding candidate material for Supercritical Water Reactor Y. Nakazono, T. Iwai, H. Abe (Univ. of Tokyo) |
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| 9479 : | Development of fuel cladding material for the next generation nuclear power reactor. Y. Kawaharada, F. Kano, T. Kaneko, K. Kitano, K. Okonogi, S. Higuchi (Toshiba) |
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| 9189 : | Overview of Welding of Oxide Dispersion Strengthened (ODS) Alloys for Advanced Nuclear Reactor Applications P. Kalvala, S. K., M. Misra, R. A. Tache (UNR) |
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|
9-11 Nuclear Fuel and Control Rod May 13 (Wed.), 3F-Room 'GRACE Room A', 09:00 - 10:30 Chair: T. Ogata (CRIEPI) |
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| * 9034 : | RESULTS OF THE QUENCH-13 REFLOOD BUNDLE TEST WITH INCORPORATION OF AN AG-IN-CD ABSORBER ROD L. K. Sepold (FZK), T. Lind (PSI), A. Pintér Csordás (AEKI), M. Steinbrueck, U. Stegmaier, J. Stuckert (FZK) |
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| 9331 : | Experimental Studies on the Transport of Silver and Cesium Fission Products in SiC T. J. Gerczak, T. Allen, L. Tan (UW) |
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| 9437 : | Effect of cold working and subsequent annealing on structural properties of Hafnium T. Mihara, H. Abe, T. Iwai, Y. Katano, N. Sekimura (Univ. of Tokyo) |
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9-12 GEN-IV Materials May 13 (Wed.), 3F-Room 'GRACE Room A', 14:00 - 15:30 Chair: W. Ryu (KAERI) |
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| 9303 : | Construction of Long-term Isochronous Stress-Strain Curves by Modeling of Short-term Creep Curves for a Grade 9Cr-1Mo Steel W. Kim, S. Yin, G. Goo (KAERI) |
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| 9432 : | Some metallic materials and fluoride salts for high temperature applications P. Hosnedl (SKODA Nuclear Machinery plc), M. J. Hron (NRI), O. Matal (ENERGOVYZKUM Ltd.) |
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| 9267 : | Corrosion of structural materials for Generation IV systems F. Balbaud-Célérier, P. Arnoux, C. Cabet, J. Courouau, L. Martinelli (CEA) |
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| * 9360 : | NEW CONCEPT OF DAMAGE EVALUATION METHOD FOR CORE INTERNAL MATERIALS CONSIDERING RADIATION INDUCED STRESS RELAXATION (1) - EXPERIMENTS AND MODELING OF RADIATION EFFECTS - Y. Miwa, K. Kondo, N. Okubo, Y. Kaji, T. Tsukada (JAEA) |
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| * 9359 : | NEW CONCEPT OF DAMAGE EVALUATION METHOD FOR CORE INTERNAL MATERIALS CONSIDERING RADIATION INDUCED STRESS RELAXATION (2) - SIMULATION OF MATERIAL DEGRADATION BEHAVIOR USING INTEGRATED MODEL - Y. Kaji, Y. Miwa, K. Kondo, N. Okubo, T. Tsukada (JAEA) |
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9-13 HTR May 12 (Tue.), 42F-Room 'TAKAO', 10:45 - 12:15 Chair: T. Ogata (CRIEPI) |
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| 9058 : | Materials for Nuclear Diffusion-Bonded Compact Heat Exchangers X. Li, T. Smith, D. Kininmont, S. Dewson (Meggitt - Heatric) |
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| * 9245 : | Irradiation Hardening of Mod.9Cr-1Mo Steel W. Ryu, S. Kim, K. Choo, D. Kim (KAERI) |
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| 9270 : | Achievements of the US-France I-NERI program on heat exchanger alloys for HTR C. Cabet (CEA), R. Wright (INL), F. Balbaud-Célérier, F. Rouillard, H. Burlet, J. Gentzbittel, P. Lamagnère (CEA), S. Dubiez-Legoff (NC), M. Blat (EdF) |
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| * 9477 : | Creep Behaviors of Nickel-Base Superalloys Alloy 617 and Haynes 230 at High Temperature D. Kim, C. Jang (KAIST), W. Ryu (KAERI) |
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| * 9326 : | Recent advances in the study of thermodynamics of FeCr and FeCr-He M. Caro (LLNL), A. Stukowski (Tech. Univ. Darmstadt), P. Erhart, B. Sadigh, A. Caro (LLNL) |
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9-14 LEB and MSR May 11 (Mon.), 47F-Room 'AOZORA', 14:00 - 15:30 Chair: F. Balbaud-Célérier (CEA), K. Itoh (NDC) |
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| 9018 : | Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor R. Lo Frano, G. Forasassi (Univ. of Pisa) |
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| 9021 : | Corrosion Resistance of Fe-Al Alloy-Coated Steel under Bending Stress in High Temperature Lead-Bismuth Eutectic E. Yamaki, M. Takahashi (TIT) |
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| * 9309 : | Corrosion of structural metallic materials for nuclear applications in molten fluorides S. Fabre (EDF), F. Balbaud-Célérier, C. Cabet (CEA), J. Finne (EDF), P. Chamelot, L. Cassayre, L. Massot (Univ. de Toulouse) |
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| Track 10: Nuclear Energy and Global Environment (3 sessions) | ||||
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10-1 Scenario Analysis and Development Plan May 11 (Mon.), 4F-Room 'KATSURA', 14:00 - 15:30 Chair: M. Uotani (JANTI) |
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| 9458 : | Proposal on Concept of Security of Energy Supply with Nuclear Energy H. Ujita, K. Matsui, E. Yamada (IAE) |
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| * 9499 : | An Analysis of Japan’s Large-scale Reduction of CO2 Emissions and Nuclear Power’s Role in its Pursuit K. Nagano (CRIEPI) |
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| 9005 : | Scenario-based Roadmapping; Assessing nuclear technology development paths for future nuclear energy system scenarios L. Van Den Durpel (LISTO), F. Roelofs (NRG), A. Yacout (ANL) |
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10-2 Biological Effects of Low Dose Radiation May 11 (Mon.), 4F-Room 'KATSURA', 15:45 - 17:15 Chair: M. Ikai (TEPCO) |
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| 9356 : | A graphical review of radiogenic animal cancer data using the “dose and dose-rate map” K. Yoshida, Y. Hoshi (CRIEPI), A. Hirasugi (JANUS), K. Sakai (NIRS) |
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| * 9357 : | Importance and Present State of the Research in Radiation-induced Bystander Responses M. Tomita (CRIEPI) |
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| * 9358 : | Significance of epidemiological and cytogenetic studies on high background radiation area residents T. Iwasaki (CRIEPI) |
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10-3 Extension of Nuclear Energy Utilization May 12 (Tue.), 4F-Room 'KATSURA', 09:00 - 10:30 Chair: K. Nagano (CRIEPI) |
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| 9213 : | Development for A Multi-Purpose Nuclear Energy Supply System T. Narabayashi, Y. Shimazu, K. Sato, M. Imamura, M. Tsuji (Hokkaido Univ.) |
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| 9449 : | Potential of Plug-in Hybrid Electric Vehicle for Reduction of CO2 Emission and Role of Non-fossil Power Plant R. Hiwatari, K. Okano, H. Yamamoto (CRIEPI) |
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| Track 11: Near Term Deployment (1 sessions) | ||||
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11-1 Near Term Deployment (1) May 12 (Tue.), 4F-Room 'KATSURA', 10:45 - 12:15 Chair: S. Bilbao y Leon (IAEA), T. Matsumura (CRIEPI), S. Kawamura (Toshiba) |
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| 9483 : | Technology Assessment of Advanced Nuclear Power Plants S. Bilbao y Leon (IAEA) |
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| 9042 : | Nuclear energy for the green development of Korea Y. K. Jeong, S. D. Lee, I. D. Kim, Y. E. Jung, B. Noh (KHNP) |
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| 9128 : | Nuclear Deployment from a Public and Political Perspective F. Roelofs, S. D. Groot (NRG) |
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| 9363 : | Small PWR "PFPWR50" using Cermet Fuel of Th-Pu particles T. Hirayama, Y. Shimazu (Hokkaido Univ.) |
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| 9370 : | A New Passive Safety FBR Concept of “KAMADO” - Easy replacement from the existing light water reactor to FBR - T. Matsumura, T. Kameyama, Y. Nauchi , I. Kinoshita (CRIEPI) |
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| 9125 : | One Plant, Three Regulators: A Case History of the Impact of Regulatory Review on EPR Design J. D. Trotter (AREVA) |
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| Track 12: Innovative and Space Reactor Systems (2 sessions) | ||||
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12-1 Space Nuclear Application May 12 (Tue.), 4F-Room 'KATSURA', 14:00 - 15:30 Chair: N. Frischauf (Qasar), K. Nabeshima (JAEA) |
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| 9373 : | Study on a Nuclear Spaceship for Interplanetary Cruise–– Core Design of a Small Fast Reactor –– T. Kitamura, Y. Yoshida, Y. Honma, T. Narabayashi, Y. Shimazu, M. Tsuji (Hokkaido Univ.) |
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| 9186 : | Proposal of Nuclear Reactors for Nuclear Electric Propulsion System T. Nishiyama, H. Nagata, H. Nakashima (Kyushu Univ.) |
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| 9371 : | Design Study of Nuclear Power Systems for Deep Space Explorers (1) Criticality of Low Enriched Uranium Fueled Core T. Kugo, H. Akie, A. Yamaji, K. Nabeshima, T. Iwamura, H. Akimoto (JAEA) |
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| 9366 : | Design Study of Nuclear Power Systems for Deep Space Explorers (2) Electricity Supply Capabilities of Solid Cores A. Yamaji, T. Takizuka, K. Nabeshima, T. Iwamura, H. Akimoto (JAEA) |
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| 9500 : | Nuclear Enhanced MHD for Multimegawatt Space Power A. Swallow, S. Anghaie (Univ. of Florida) |
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| 9469 : | The MOA Thruster - a high Performance Plasma Accelerator using Alfven Waves for for Nuclear Power and Propulsion Applications N. Frischauf, M. Hettmer, A. Grassauer, T. Bartusch (Qasar), O. Koudelka (Graz Univ. of Tech.) |
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12-2 Innovative Nuclear Systems May 12 (Tue.), 4F-Room 'KATSURA', 15:45 - 17:15 Chair: T. Kugo (JAEA), H. Nakashima (Kyushu Univ.) |
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| 9350 : | Modification of Japanese First Nuclear Ship Reactor for a Regional Energy Supply System Using Gadolinia as a Burnable Poison K. Sato, Y. Shimazu, T. Narabayashi, M. Tsuji (Hokkaido Univ.) |
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| 9343 : | Library Dependency of Effective Multiplication Factor in Thorium Molten Salt Reactor Y. Kamiyama, Y. Shimazu, T. Narabayashi, M. Tsuji (Hokkaido Univ.) |
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| 9353 : | Innovative nuclear system based on liquid fuel S. Delpech, E. Merle-Lucotte, X. Doligez, S. Jaskierowicz, D. Heuer, G. Picard (CNRS) |
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| 9111 : | Research for the Supercritical Carbon Dioxide Brayton Cycle Energy Conversion System related with Gen-IV SFR J. Cha, J. Eoh, T. Lee, S. Sung, S. Kim (KAERI), T. Kim, K. Suh (SNU), D. Kim, M. Kim (POSTECH) |
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| * 9039 : | Concept of Small Reactor for Neutron Transmutation Doping using PWR type fuel elements T. Obara, P. Liem (TIT), H. Yagi (TEPCO) |
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| Track 13: Infrastructure to Deploy World Nuclear (2 sessions) | ||||
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13-1 Session(1) May 13 (Wed.), 4F-Room 'KEYAKI', 09:00 - 10:30 Chair: S. E. Pickett (Univ. of Tokyo) |
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| 9519 : | Future Scenarios for the Development of Nuclear Power S. E. Pickett (Univ. of Tokyo) |
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| * 9498 : | Supply Guarantee Initiatives for Nuclear Fuel Materials and Services and Their Compatibility with the Market K. Nagano (CRIEPI) |
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| 9508 : | Project Based Learning for Reactor Engineering Education T. Narabayashi, M. Tsuji, Y. Shimazu (Hokkaido Univ.) |
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13-2 Session(2) May 13 (Wed.), 4F-Room 'KEYAKI', 10:45 - 12:15 Chair: K. Matsui (IAE) |
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| 9230 : | SUPPORT SERVICES FOR NEW NUCLEAR POWER PLANT PROJECTS A. B. Manrique, F. Cazorla (TECNATOM,SA) |
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| 9321 : | A PARADIGM SHIFT NEEDED FOR NUCLEAR REACTORS: FROM ECONOMIES OF UNIT SCALE TO ECONOMIES OF PRODUCTION SCALE N. Li (Xiamen Univ.) |
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| 9322 : | LOS ALAMOS NUCLEAR ENTERPRISE RESOURCE AND INFRASTRUCTURE MODEL (LA-NERIM) N. Li (Xiamen Univ.), C. Dale, K. Kern, S. Scott (LANL) |
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