19th International ConferenceOn Nuclear Engineering in Osaka (ICONE19 Osaka)
- Energy Strategy for the Nuclear Era Decoupled from Fossil -
October 24 - 25, 2011. Osaka University, Japan
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Session 24 A-1 (11:10 - 13:10)
Session Chair, Co-chair
Satoshi Kurata, Chubu Electric Power Co
Joe Miller, EDA, Inc.
TRK 1 Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant Expand All Sessions In Track
Track Chair: Satoshi Kurata, Chubu Electric Power Co.
Track Co-Chair: Koji Yamada, Chubu Electric Power Co.,Inc.
Track Co-Chair: Motonari Haraguchi, Hitachi Ltd.
Track Co-Chair: Joe Miller, EDA, Inc.
Track Co-Chair: Xinrong LIU, China Nuclear Power Engineering Co.,Ltd
ICONE19-44012
NUCLEAR POWER PLANT PERFORMANCE MONITORING USING DATA VALIDATION AND RECONCILIATION (DVR) EAPPLICATION AT THE BRAZILIAN ANGRA 2 PWR PLANT
Anh Tho Tran Quang, BELSIM S.A.
ICONE19-43133
Applying the Real Options Approach on Nuclear Power Project Decision Making
Haitao Song, State Nuclear Power Engineering Corporation (China)
ICONE19-43948
DEVELOPING MAINTENANCE TECHNOLOGIES FOR FBR's HEAT EXCHANGER UNITS by ADVANCED LASER PROCESSING
Akihiko NISHIMURA, Japan Atomic Energy Agency
ICONE19-43397
Study on Comprehensive and coordination construction and operation mode of nuclear power plant to power grid
Wang Lu, GuangDong Electrical Design Institute(GEDI), China
ICONE19-43398
USING THREE-DIMENSION VIRTUAL REALITY MAIN CONTROL ROOM FOR INTEGRATED SYSTEM VALIDATION AND HUMAN RELIABILITY ANALYSIS
Chih-Wei Yang, Institute of Nuclear Energy Research, Taiwan
TRK 2 Component Reliability and Materials Issues Expand All Sessions In Track
Track Chair: Hidenori Takahashi, Toshiba
Track Co-Chair: yoshihiro isobe, nuclear fuel industries ltd.
Track Co-Chair: chiaki kato, Japan Atomic Energy Agency
Track Co-Chair: Jovica Riznic, Canadian Nuclear Safety Commission
Track Co-Chair: Guoqiang Wang, Westinghouse Electric Company LLC
Track Co-Chair: Eberhard Altstadt, Helmholtz-Zentrum Dresden-Rossendorf
Track Co-Chair: Wei Huang, Nuclear Power Insitiute of China
ICONE19-43194
EFFECT OF THERMO-MECHANICAL PROCESSING VARIABLES ON MICROSTRUCTURE, TEXTURE AND PROPERTIES OF COLD WORKED ZR-2.5NB ALLOY DURING FABRICATION OF PRESSURE TUBE FOR PHWR
Nudurupati Saibaba, Nuclear Fuel Complex, Hyderabad, India
ICONE19-43291
Development of laser peening technology for low pressure turbine blades
Itaru Chida , Toshiba Corporation
ICONE19-43201
Flaw Evaluation of Cracks in Shroud Support Welds of Tokai-2
Koji Dozaki, The Japan Atomic Power Company
ICONE19-43979
The Effect of Mechanical Loading on Residual Stress Induced by Laser Peening
Toshiyuki Tazawa, Toshiba Corporation
Session 24 A-2 (14:00 - 16:00)
Session Chair, Co-chair
Koji Yamada, Chubu Electric Power Co.,Inc.
Guoqiang Wang, Westinghouse Electric Company LLC
ICONE19-44017
INFLUENCE OF THE RESIDUAL STRESSES AND STRAINS GENERATED BY HEAT TREATMENTS ON THE HYDROGEN EMBRITTLEMENT OF A NUCLEAR REACTOR PRESSURE VESSEL
J. Toribio, Dept. of Materials Engineering, University of Salamanca,
ICONE19-43175
Simplified Evaluation Method of Strain Rate Being Generated on Structural Materials During Plant Start-up
Koji Dozaki, The Japan Atomic Power Company
ICONE19-43877
Prediction of Residual Stress Improvement by Water Jet Peening (WJP) Using Cavitating Jet and Residual Stress Simulations
Masashi Fukaya, Hitachi, Ltd
ICONE19-43221
Planning of Environmental Mitigation for Stress Corrosion Cracking of BWR Core Internals by Means of Noble Metal Chemical Addition and of Electrochemical Corrosion Potential Measurement
Yutaka Ueyama , The Japan Atomic Power Company
ICONE19-43499
Experimental Study on Diffusion of Metals in Lead-Bismuth Eutectic in A Thin Tube
Eriko Irisawa-Yamaki, Tokyo Institute of Technology
ICONE19-43141
HIGH TEMPERATURE OXIDATION OF FBR STRUCTURAL MATERIALS IN CARBON DIOXIDE AND IN AIR
Tomohiro FURUKAWA, Japan Atomic Energy Agency
ICONE19-43174
Microstructural Studies of Zr-2.5Nb and Zircaloy-2 Pressure Tubes Irradiated in Indian Pressurized Heavy Water Reactors.
Dinesh srivastava, Bhabha Atomic Research Center, Mumbai, India
ICONE19-43658
DEFECT DETECTABILITY OF EDDY CURRENT TESTING FOR UNDERWATER LASER BEAM WELDING
Souichi Ueno, Toshiba Corp
ICONE19-43166
MICROSTRUCTURAL AND POSITRON ANNIHILATION STUDIES OF HYDRIDE PHASE FORMATION IN SINGLE AND TWO PHASE ZIRCONIUM BASE ALLOYS
Dinesh Srivastava, BARC, Trombay, Mumbai
Session 24 A-3 (16:00 - 18:00)
Session Chair, Co-chair
Qiusheng Liu, Kobe University
Ernie Hauser, Cameron Measurement Systems, Caldon Ultrasonics
TRK 10 Computational Fluid Dynamics (CFD) and Coupled Codes
Track Chair: Akira Yamaguchi, Graduate shool of Engineering , Osaka University
Track Co-Chair: Hiroyuki Ohshima, JAEA
Track Co-Chair: Muftuoglu Kurshad, GE Hitachi Nuclear Energy
Track Co-Chair: Nikolay Kolev, Siemens
Track Co-Chair: Richard Johnson, Idaho National Laboratory
Track Co-Chair: Yassin Hassan, Department of Nuclear Engineering
Track Co-Chair: Liangzhi Cao, Xi'an Jiaotong University
Track Co-Chair: Ludwig Haber, Alden Research Laboratory
ICONE19-44013
ROD EJECTION ACCIDENT BY THE COUPLED SYSTEM CODE ATHLET-QUABOX/CUBBOX
Yann Périn, GRS mbH
ICONE19-43986
Development of PIRT and Assessment Matrix for V&V of Sodium Fire Analysis Codes
Shuji Ohno, JAEA
ICONE19-43730
Numerical Investigation on Large-scale Eddy Structure in Unsteady Pipe Elbow Flow at High Reynolds Number Conditions with Large Eddy Simulation Approach
Masaaki Tanaka, JAEA
ICONE19-44127
STUDY ON TURBULENT MODELING IN GAS ENTRAINMENT EVALUATION METHOD
Kei Ito, JAEA
ICONE19-44132
SIX DIFFERENT TURBULENCE MODELS AND EXPERIMENTS COMPARISONS ON THERMAL MIXING PHENOMENON IN A TEE PIPING
Chao Jen Li, Industrial Technology Research Institute
ICONE19-43076
A CFD Study of the Flow Field and Aerodynamic Torque on a Triple-offset Butterfly Valve Used in Nuclear Power Plant
Qinzhao Zhang, Tsinghua University
ICONE19-43534
Numerical Simulation of Dynamic Flow Structure and Thermal Stratification Phenomena in LMFBR
Makoto Shibahara , Osaka University
ICONE19-43453
EFFECTS OF TURBULENCE NEAR A FREE SURFACE ON THE DYNAMICS OF TWO-PHASE FLOW
Ken Uzawa, JAEA
Session 24 B-1 (11:10 - 13:10)
Session Chair, Co-chair
Hideaki Heki, Toshiba Corporation
Leon Cizelj, Jožef Stefan Institute
TRK 3 Structural Integrity
Track Chair: Kazuyuki Tsukimori, Japan Atomic Energy Agency
Track Co-Chair: Kenji Takahashi, Mitsubishi Heavy Industries,LTD.
Track Co-Chair: Asif Arastu, Bechtel Power Corporation
Track Co-Chair: Leon Cizelj, Jožef Stefan Institute
Track Co-Chair: Zhenmao Chen, Xi'an Jiaotong University
Track Co-Chair: Qing Mao, China Nuclear Power Engineering Co., LTD
ICONE19-43961
Performance Analysis of Passively Safe BWR with Experimental and Numerical Simulation
Jun Yang, Purdue University
ICONE19-43121
A Generic Model for Residual Compressive Strength of Concrete after Fire in Nuclear Power Plants
yihai li, Guangdong Electric Power Design Institute, China
ICONE19-43440
SPECTRAL ELEMENT MODEL FOR THE AXIAL-BENDING-SHEAR COUPLED VIBRATION OF A COMPOSITE TIMOSHENKO BEAM
Usik Lee, Inha University
ICONE19-43489
PRESSURIZED WATER REACTOR VESSEL INTERNALS GUIDE TUBE GUIDE CARD WEAR AGING MANAGEMENT
Ibrahim Mohammed, Westinghouse Electric Company
TRK 4 Nuclear Technology Applications and Innovations
Track Chair: Ikuo Ioka, Japan Atomic Energy Agency
Track Co-Chair: Toshiharu Muramatsu, Japan Atomic Energy Agency
Track Co-Chair: Romney Duffey, AECL
Track Co-Chair: Ivo Kljenak, Jozef Stefan Institute
Track Co-Chair: Danrong Song, Nuclear Power Institute of China
Track Co-Chair: Chaohui He, Xian Jiaotong University
ICONE19-44128
PHENOMENOLOGICAL EVALUATION OF LASER-IRRADIATED WELDING PROCESSES WITH A COMBINED USE OF HIGHER-ACCURACY EXPERIMENTS AND COMPUTATIONAL SCIENCE METHODOLOGIES (3)IN-SITU OBSERVATIONS OF WELDED POOL USING AN INTENSE X-RAY BEAM
Tomonori Yamada, Japan Atomic Energy Agency
ICONE19-43910
Design of radiation shielding for the CPHS target station
B. Zhong, Tsinghua University
TRK 5 Advanced Reactors and Near Term Deployment
Track Chair: Hideaki Heki, Toshiba Corporation
Track Co-Chair: Dmitry Paramonov, Westinghouse
Track Co-Chair: Annalisa Manera, Paul Scherrer Institute
Track Co-Chair: Kan WANG, Tsinghua University
Track Co-Chair: Dongsheng Li, China Nuclear Power Technology Research Institute
ICONE19-43842
EVALUATION OF DAMAGES OF AIRPLANE CRASH IN EUROPEAN ADVANCED BOILING WATER REACTOR (EU-ABWR)
Kazuhiro Kamei, Toshiba Corporation
ICONE19-43646
A Study for Small - medium LWR Development of JAPC
Toshihiko Okazaki, Japan Atomic Power Company
Session 24 B-2 (14:00 - 16:00)
Session Chair, Co-chair
Yoshiyuki Narumiya., Kansai Electric Power Co
Xinrong LIU, China Nuclear Power Engineering Co.,Ltd
TRK 6 Safety and Security Expand All Sessions In Track
Track Chair: Kohei Hisamochi, Hitachi-GE Nuclear Energy, Ltd.
Track Co-Chair: Nobuyuki Ueda, central Research Institute of Eelctric Power Industry
Track Co-Chair: Martin Sattison, Idaho National Laboratory
Track Co-Chair: Jianqiang Shan, Xi'an Jiaotong University
ICONE19-43321
Development of Integrated Parameter Database for Risk Assessment at the Rokkasho Reprocessing Plant
Yoshikazu Tamauchi, Japan Nuclear Fuel Limited
ICONE19-43422
EXPERIMENTAL STUDY ON THERMAL INTERACTION OF ETHANOL JETS IN HIGH TEMPERATURE FLUORINERT
Rongyuan Sa, Tokyo institute of Technology
ICONE19-43100
AIR INGRESS ANALYSIS OF CHIMNEY EFFECT FOR SIMULTANEOUS RUPTURE OF TWO PRIMARY PIPES IN THE HTR-PM
Zheng Yanhua, INET, Tsinghua University
ICONE19-43784
A TRANSIENT MODELING OF A HELIUM TURBINE POWER SYSTEM
Heng Xie, Jie Wang, Institute of Nuclear Engineering Technology, Tsinghua University
ICONE19-43276
Preliminary study on In-Vessel Retention in large-scale advanced PWR
Hong XU, State Nuclear Power Technology Research & Development Centre, Beijing
ICONE19-43410
ANALYSIS OF HYDROGEN MITIGATION IN A SEVERE ACCIDENT
Jie Zou, School of Mechanical Engineering, Shanghai Jiaotong University, Shanghai
ICONE19-43286
REDEFINING INTERRELATIONSHIP BETWEEN NUCLEAR SAFETY, NUCLEAR SECURITY AND SAFEGUARDS
Kazutomo Irie, Japan Nuclear Energy Safety Organization/ The University of Tokyo
ICONE19-43782
Reaction Path Analysis of Sodium-Water Reaction Phenomena in support of Chemical Reaction Model Development
Shin Kikuchi, Japan Atomic Energy Agency
ICONE19-43435
VARIA - AN APPLICATION FOR MASS COMPUTING AND STATISTICAL ANALYSIS OF THE SIMULATION RESULTS IN BEPU SAFETY ASSESSMENT
Evgeny V. Moiseenko, Nuclear Safety Institute of Russian Academy of Sciences (IBRAE RAN)
Session 24 B-3 (16:00 - 18:00)
Session Chair, Co-chair
Yuichiro Yoshimoto, Hitachi-GE Nuclear Energy
Shi Lei, CNS, INET, Tsinghua University
TRK 7 Codes, Standards, Licensing and Regulatory Issues Expand All Sessions In Track
Track Chair: Tetsuya Nagata, Hitachi-GE Nuclear Energy
Track Co-Chair: Ralph Hill, Westinghouse Electric Company
Track Co-Chair: Aleksandr Kroshilin, VNIIAES
Track Co-Chair: Lingfu Zeng, ÁE-Industry AB
Track Co-Chair: Xuewu Cao, Shanghai Jiao Tong University
ICONE19-43272
OPINIONS ON DEVELOPMENT OF CHINA NUCLEAR POWER STANDARD SYSTEM
Huangweifeng Zhengjunming, General Design Division General Design Division, China Nuclear Power Engineering Co.,Ltd.
ICONE19-43364
USING PROBABILISTIC SAFETY ASSESSMENTS IN OPERATING TECHNICAL SPECIFICATIONS: RECONCILING RISK INSIGHTS AND PRACTICAL PLANT CONSIDERATIONS
Isaac Malgas, Eskom, Generation Koeberg Nuclear Power Station, South Africa
ICONE19-43382
STUDY ON THE NEAR SURFACE DISPOSAL OF LILW IN CHINA
Wentang Zheng, Guangdong electric power design institute
TRK 8 Fuel Cycle, Radioactive Waste Management and Decommissioning Expand All Sessions In Track
Track Chair: Tsutomu Baba, Japan Nuclear Energy Safety Organization
Track Co-Chair: Morimasa Naito, Japan Atomic Energy Agency
Track Co-Chair: Patricia Paviet-Hartmann, Idaho National Laboratory
Track Co-Chair: Pavel Poluektov, Bochvar Institute
Track Co-Chair: Hubert Druenne, Tractebel - GDF SUEZ
Track Co-Chair: Xuegang Liu, Tsinghua University,Beijing, China
ICONE 19- 43519
Preliminary Research on Thorium-Uranium Fuel Cycle Characteristic in PWR
Wei Chunlin, Tsinghua University, Beijing
ICONE19-43160
Development of Spent Ion Exchange Resin Processing in Nuclear Power Stations
Yasutomi Morimoto, JGC Corporation, Research and Development Center
ICONE19-43801
OUTLINE OF LAUNDRY DRAINAGE TREATMENT SYSTEM COMBINING CATALYTIC OXIDATION AND FILTRATION
Masanori Kanda, NGK insulators, Ltd
ICONE19-43560
Interpretation of Hydrogeological Characteristics based on Data from Long-Term Cross-Hole Pumping Test
Hironori ONOE, Japan Atomic Energy Agency
ICONE19-43388
A calculation of spatial range of colloidal silicic acid deposited downstream from the alkali front
Yuichi Niibori, Dept. of Quantum Science & Energy Engineering, Tohoku University
ICONE19-43234
RADIOLOGICAL CHARACTERIZATION FOR SMALL TYPE LIGHT WATER REACTOR
Ken-ichi Tanaka, Japan Atomic Power Company
ICONE19-43255
A preliminary study on the transport behavior for a potential disposal site of LILW in southern China
Shuping Yi, Guongdong Electric Power Design Institute, China
Session 24 C-1 (11:10 - 13:10)
Session Chair, Co-chair
Guanghui Su, Xi'an Jiaotong University
Yoshihisa Nishi, Central Research Institute of Electric Power
TRK 9 Thermal Hydraulics
Track Chair: Kazuyuki Takase, Japan Atomic Energy Agency
Track Co-Chair: Hiroyasu Ohtake, Kogakuin University
Track Co-Chair: Michitsugu Mori, Tokyo Electric Power Co., Inc.
Track Co-Chair: Yasushi Yamamoto, Toshiba Corporation
Track Co-Chair: SHINICHI MOROOKA, Japan/Waseda University
Track Co-Chair: Richard Schultz, Idaho National Laboratory
Track Co-Chair: Yassin Hassan, Department of Nuclear Engineering
Track Co-Chair: Guanghui Su, Xi'an Jiaotong University
ICONE19-43529
Validation of Coupled Neutron Kinetics and Thermal Hydraulics Analysis Code SKETCH-INS/TRACE5.0 and Application to Statistical Safety Evaluation of BWR Loss of Load Transient
Ryoko ICHIKAWA, Japan Nuclear Energy Safety Organization
ICONE19-43592
Improvement of MARS Code Reflood Model
Moonkyu Hwang, Korea Atomic Energy Research Institute
ICONE19-43969
RELAP5 Analysis of OECD/NEA ROSA-2 Project Experiments on Intermediate-break LOCAs at Hot Leg or Cold Leg
Takeshi TAKEDA, Japan Atomic Energy Agency (JAEA)
ICONE19-43568
MODELING OF DYNAMIC INSTABILITIES IN BOILING SYSTEMS
L.C.Ruspini, Department of Energy and Process Engineering, NTNU, Norway
ICONE19-43043
Investigation of Wall Temperature Fluctuations by Visualization Tests for Steam-Water Two-Phase Flow in the Pressurizer Spray Piping
Koji Miyoshi, Institute of Nuclear Safety System, Inc.
ICONE19-43538
Visualization of Cavitation Flow Field Downstream from an Orifice
Yukinori NAGAYA, Institute of Nuclear Safety System, Inc.
ICONE19-43258
Visualization of Bubble Size Distribution in Inclined Rectangular Channel
Gang Hong, CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics
ICONE19-43607
APPLICATION OF CONSTANT ELECTRIC CURRENT METHOD IN DISPERSED BUBBLY FLOW
Shin-ichiro UESAWA, University of Tsukuba
ICONE19-44020
Multi-dimensional Two-Phase Flow Measurements in a Large-Diameter Pipe Using Wire-Mesh Sensor
Taizo KANAI, Central Research Institute of Electric Power Industry
ICONE19-44019
LIQUID FILM THICKNESS MEASUREMENT IN SMALL SQUARE PIPE USING ULTRASONIC PULSE-ECHO METHOD
Goro AOYAMA, Hitachi, Ltd.
ICONE19-43085
Prediction of Critical Heat Flux in Narrow Rectangular Channels Using an Artificial Neural Network
Zhou Lei, CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China
ICONE19-43852
NUCLEATE BOILING HEAT TRANSFER AND CRITICAL HEAT FLUX IN TITANIUM DIOXIDE-WATER NANOFLUIDS
Tomio Okawa, Department of Mechanical Engineering, Osaka University
Session 24 C-2 (14:00 - 16:00)
Session Chair, Co-chair
Kenichi Kubota, Toshiba Corporation
He Keyu, China Nuclear Power Engineering Co.,Ltd.
ICONE19-44124
Development of PIRT for Fast Reactor under Natural Circulation Decay Heat Removal Operations
Norihiro Doda, JAEA
ICONE19-43704
Modeling on Bubbly to Churn Flow Pattern Transition for Vertical Upward Flows in Narrow Rectangular Channel
Yanlin Wang, Nuclear Power Institute of China
ICONE19-43535
COMPARISON OF THE WATER AND SODIUM CAVITATION PHENOMENA IN VENTURI
Teddy Ardiansyah, Tokyo Institute of Technology
ICONE19-43900
PREDICTION OF BYPASS FLOWS IN HTR-PM BYTHE FLOW NETWORK METHOD
Jun Sun, INET, Tsinghua University
ICONE19-43309
ANALYSIS ON ATWS CAUSED BY EARTHQUAKE OF THE HTR-10GT
Lang Minggang , Tsinghua University, Beijing China
ICONE19-43192
STUDY ON HIGH SPEED LITHIUM JET FOR NEUTRON SOURCE OF BORON NEUTRON CAPTURE THERAPY (BNCT)
Minoru Takahashi, Tokyo Institute of Technology
ICONE19-43977
Development of Prediction Technology of Two-Phase Flow Dynamics under Earthquake Acceleration (1) Numerical Simulation of Two-Phase Flow Behavior under Earthquake Acceleration
Hiroyuki Yoshida, Japan Atomic Energy Agency
ICONE19-44166
Development of Prediction Technology of Two-Phase Flow Dynamics under Earthquake Acceleration (2) - Experimental Study on Flow Rate Fluctuation -
Hideaki Monji, University of Tsukuba
ICONE19-44150
Development of Prediction Technology of Two-Phase Flow Dynamics under Earthquake Acceleration (3) -The effect of structure vibration on bubbly flow behavior-
Kousuke Mizuno, University of Tsukuba
ICONE19-43222
Countercurrent Air-Water Tests Using a Scale Model of a Pressurizer Surge Line
Chihiro Yanagi, Institute of Nuclear Safety System, Inc.(INSS)
Session 24 C-3 (16:00 - 18:00)
Session Chair, Co-chair
Hiroyuki Yoshida, Japan Atomic Energy Agency
Asif Arastu, Bechtel Power Corporation
ICONE19-43528
EFFECT OF SOLIDIFICATION ON BREAKUP BEHAVIOR DURING MOLTEN MATERIAL JET AND COOLANT INTERACTION
Takashi Wada, University of Tsukuba
ICONE19-43982
SIMULATION OF SOLID-LIQUID MULTIPHASE FLOWS WITH FUEL RELOCATION AND FREEZING BEHAVIOR IN PIN BUNDLE GEOMETRY
Md. Abdul Malek Soner, Kyushu University
ICONE19-43284
HEAT AND MOMENTUM TRANSFER MECHANISMS UNDER THE DIRECT-CONTACT-CONDENSATION BETWEEN SUPERSONIC STEAM FLOW AND WATER JET
Shunsuke Shibayama, University of Tsukuba
ICONE19-43556
Bubble behavior in subcooled flow boiling in a vertical rectangular channel
ROUHOLLAH AHMADI, Osaka University
ICONE19-43523
Farther study on transient boiling phenomena generated by microwave heating
Shota Suzuki, University of Tsukuba
ICONE19-43407
EXPERIMENTAL STUDY IN INFLUENCE OF FLOW STRUCTURE ON JET SURFACE FRAGMENTATION
Taihei Kuroda, Univercity of Tsukuba
ICONE19-43421
Nuclear reaction analysis for composition measurement of BN thin films
T. Kobayashi, Tsuyama National College of Technology
ICONE19-43556
Bubble behavior in subcooled flow boiling in a vertical rectangular channel
ROUHOLLAH AHMADI, Osaka University
ICONE19-43284
HEAT AND MOMENTUM TRANSFER MECHANISMS UNDER THE DIRECT-CONTACT-CONDENSATION BETWEEN SUPERSONIC STEAM FLOW AND WATER JET
Shunsuke Shibayama, University of Tsukuba
ICONE19-43407
EXPERIMENTAL STUDY IN INFLUENCE OF FLOW STRUCTURE ON JET SURFACE FRAGMENTATION
Taihei Kuroda, Univercity of Tsukuba
ICONE19-44189
THE EFFECT OF RICE HUSK ASH ADDITION AND SAND VOLUME VARIATION ON LIQUID RADIOACTIVE WASTE CEMENTATION
Saiful A. Nugroho, GadjahMada University, Indonesia
ICONE19-43348
MEASUREMENT OF NON-EQUIBIAXIAL RESIDUAL STRESS FIELD BY INDENTATION TECHNIQUE USING ASYMMETRIC INDENTER
Houichi Kitano, Osaka University
ICONE19-43024
Effect of the two phase flow models in the nuclear reactor single channel stability analysis
Jiyun Zhao, Nanyang Technological University, China
Session 24 D-1 (11:10 - 13:10)
Session Chair, Co-chair
Hiroshige Kikura, Tokyo Institute of Technology
Tao Zhou, Chinese Academy of Sciences
TRK 16 Student Paper Competition
Track Chair: Hiroshige Kikura
Track Co-Chair: Tomio Okawa, Osaka University
Track Co-Chair: Igor Pioro, University of Ontario Institute of Technology
Track Co-Chair: Sama Bilbao y Leon, Virginia Commonwealth University
Track Co-Chair: Wolfgang Hansen, Technical University Dresden
Track Co-Chair: Suyuan Yu, INET, Tsinghua University
Track Co-Chair: Suizheng Qiu, Xi'an Jiaotong University
ICONE19-43420
INVESTIGATION OF FLOW STRUCTURE TRANSITION IN LOWER PLENUM OF ABWR
Shun Watanabe, University of Tsukuba
ICONE19-43507
THERMAL ASPECTS OF USING ThO2 IN A 54- AND 64-ELEMENT FUEL BUNDLE DESIGNED FOR SCWR APPLICATION
Krysten King, University of Waterloo (Canada)
ICONE19-43858
An improved critical heat flux prediction model for subcooled and low quality flow boiling under motion condition based on microscopic mechanism
Wenxing LIU, Xi'an Jiaotong University (China)
ICONE19-44082
EFFECT OF HEAT TRANSFER COEFFICIENT ON SHEATH AND FUEL CENTRELINE TEMPERATURES IN SCWRS
Lisa Grande, University of Ontario Institute of Technology (Canada)
ICONE19-43109
STUDY ON BOILING HEAT TRANSFER OF MINI-HEAT TRANSFER SURFACE IN NARROW CHANNELS
Yoshiki Morita, Shinshu University
ICONE19-43215
NUMERICAL RESEARCH ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD
Hua Li, , Xi'an Jiaotong University (China)
ICONE19-43248
Experimental study on method for heat transfer enhancement using a porous material
Takuya Shimura, University of Yamanashi
ICONE19-43503
DEVELOPING A HEAT-TRANSFER CORRELATION FOR SUPERCRITICALWATER FLOWING IN VERTICAL TUBES AND ITS APPLICATION IN SCWRS
Sahil Gupta, University of Ontario Institute of Technology (Canada)
ICONE19-43617
THE STUDY OF VELOCIMETRY IN HIGH TEMPERATURE FLOW
Tomonori Ihara, Tokyo Institute of Technology
ICONE19-43509
A RELATIONSHIP BETWEEN THE MOTION OF A ZIGZAGGING BUBBLE AND ITS WAKE
Rintarou Tachibana, Shizuoka university
ICONE19-44083
WHOLE-FIELD VELOCITY MEASUREMENTS OF ISOTHERMAL BUBBLE PLUME USING PTV
Abdul Khan, Texas A&M University (USA)
ICONE19-43240
EFFECTS OF HOMOGENEOUS GEOMETRY MODELS IN SIMULATING THE FUEL BALLS IN HTR-10
Jinn-Jer Peir, National Tsing Hua University (Taiwan)
ICONE19-44066
THE TRIGONAL NODAL SP3 METHOD OF THE REACTOR CODE DYN3D
Susan Duerigen, Helmholtz-Zentrum Dresden-Rossendorf (Germany)
ICONE19-43235
DEVELOPMENT OF A MONTE CARLO MULTI-GROUP CONSTANTS GENERATION CODE
Mancang Li, Tsinghua University (China)
ICONE19-43237
EVALUATION OF PHYSICAL PROPERTIES OF SIMULATED PLUTONIUM INERT MATRIX FUEL OF VARYING DENSITIES WITH THERMAL SHOCK EXPERIMENTS
Nadia Rohbeck , Lehrstuhl Wasserstoff-und Kernenergietechnik, Technische Universität Dresden (Germany)
ICONE19-43803
HEAT-TRANSFER CALCULATIONS OF A RE-ENTRANT CHANNEL FOR PRESSURE-TUBE SCWRS
Eugene Saltanov, University of Ontario Institute of Technology (Canada)
ICONE19-43288
TUDY ABOUT SUSTAINABLE SCENARIO OF NUCLEAR FUEL CYCLE IN CHINA
Yilin KONG, Tohoku University
Session 24 D-2 (14:00 - 16:00)
Session Chair, Co-chair
Tomio Okawa, Osaka University
Mamoru Ishii, Purdue University
ICONE19-43372
Numerical Simulation of Opposing Mixed Convection Heat Transfer of Lithium-Lead in a Vertical Square Channel with Heat Source
Weifeng Ni, Xi'an Jiaotong University (China)
ICONE19-43691
Thermalhydraulic Analysis of Uranium Carbide (UC) Fuel in 54 and 64-Element Fuel Bundles for SCWRs
Arif Qureshi, University of Ontario Institute of Technology (Canada)
ICONE19-43492
STUDY OF SELECTED TURBULENT MODELS FOR SUPERCRITICAL WATER HEAT TRANSFER IN VERTICAL BARE TUBES USING CFD CODE FLUENT-12
Amjad Farah, University of Ontario Institute of Technology (Canada)
ICONE19-43654
SIMULATION OF HYDROGEN DEFLAGRATION EXPERIMENTS IN THE ENACCEF FACILITY USING ASTEC CODE
Mantas Povilaitis, Lithuanian Energy Institute
ICONE19-43773
EFFECT OF GAP CONDUCTANCE ON HIGH THERMAL-CONDUCTIVITY FUELS IN SUPERCRITICAL WATER-COOLED REACTORS (SCWRS)
Wargha PeimanEUniversity of Ontario Institute of Technology (Canada)
ICONE19-43981
Numerical Simulation of Effective Viscosity in Solid-Fluid Mixture Flows Using Finite Volume Particle Method
Takahito Suzuki, Kyushu University
ICONE19-43281
MEASUREMENT OF MASS TRANSFER COEFFICIENT IN DIRECT CONTACT SULFURIC ACID CONCENTRATION FOR IS PROCESS
Katsuteru Sugiyama, University of Tsukuba
ICONE19-43635
MODERATOR HEAT-LOSS ANALYSIS OF A CERAMIC-INSULATED RE-ENTRANT SCWR FUEL-CHANNEL
Jeffrey Samuel, University of Ontario Institute of Technology (Canada)
ICONE19-43021
PARAMETER DESIGN AND OPTIMIZATION OF TIGHT-LATTICE ROD BUNDLES
Chunhui DAI , Xi'an Jiaotong University (China)
ICONE19-43238
EXPERIMENTAL AND THEORETICAL STUDIES OF THE WALL BOUNDARY REGION "HEAVY LIQUID-METAL
Kirill Makhov, Nizhny Novgorod State Technical University by R.E. Alekseev
ICONE19-43644
TEMPERATURE PROFILES OF A VERTICAL BARE 7-ELEMENT BUNDLE COOLED WITH SUPERCRITICAL FREON-12
Graham Richards, University of Ontario Institute of Technology
ICONE19-43210
EXPERIMENTAL STUDY OF LIQUID-METAL TARGET DESIGNS OF ACCELERATING-CONTROLLED SYSTEMS
Mikhail Iarmonov, Nizhny Novgorod State Technical University by R.E. Alekseev
ICONE19-43640
INTERMEDIATE DOUBLE-PIPE HEAT EXCHANGER FOR THERMOCHEMICAL HYDROGEN CO-GENERATION WITH SCW NPP
Andrew Lukomski, University of Ontario Institute of Technology (Canada)
ICONE19-43522
A Partial Factor-Based Approach for the Assessment of Nuclear Piping Vulnerable to Corrosion
Xufang Zhang, University of Waterloo (Canada)
ICONE19-43734
Development of Cesium Trapper and Single-Gas-Bubble Injector into Sodium Pool
Kazuki Mizutani, Hokkaido university
ICONE19-44184
RADIOLOGICAL CONSEQUENCES ANALYSIS FOR POSTULATED LBLOCA ON PWR 1300 AT MURIA PENINSULA
Irwan Ferdiansyah, Gadjah Mada University (India)
ICONE19-43162
EFFECT OF GRAVITY ON DISTRIBUTION PARAMETER AND DRIFT VELOCITY IN VERTICAL UPWARD BUBBLY TWO-PHASE FLOW
Yusuke Shimomura, Tokyo University of Marine Science and Technology
ICONE19-43876
UPDATED HEAT TRANSFER CORRELATIONS FOR SUPERCRITICAL WATERCOOLED REACTOR APPLICATIONS
Sarah Mokry, University of Ontario Institute of Technology
Session 24 D-3 (16:00 - 18:00)
Session Chair, Co-chair
Igor Pioro, University of Ontario Institute of Technology
Fumio Kasahara, Japan Nuclear Energy Safety Organization (JNES)
ICONE19-43127
Thermal Hydraulic Analysis of Thermal Stratification in Pressurizer Surge Line
Yang Mengjia, China Guangdong Nuclear Power Engineering CO.,LTD.
ICONE19-43525
EVALUATION OF HEAT LOSS AND WATER TEMPERATURE IN A SPENT FUEL PIT
Michio Murase, Institute of Nuclear Safety System, Inc
ICONE19-43830
Numerical Simulation of Two-phase Critical Flow with the Phase Change in the Nozzle Tube
Masahiro Ishigaki, Japan Atomic Energy Agency
ICONE19-43627
Best Estimate Probabilistic Safety Assessment Results for the Westinghouse Advanced Loop Tester (WALT)
Guoqiang Wang, Westinghouse Electric Company LLC
ICONE19-43273
INVESTIGATION OF CRITICAL HEAT FLUX IN THE ROD BUNDLE USING MECHANISTIC APPROACH IN CONJUNCTION WITH THE SUBCHANNEL CODE
Dinesh Chandraker, Bhabha Atomic Research Centre, India
ICONE19-43123
Reduced Height Effect on the PWR's Integral Test Facility during Long Term Cooling
Yuquan Li, State Nuclear Power Technology R&D Center, China
ICONE19-43809
Analysis of thermal-hydraulic performance on Starting Methods of IPWR
Liang Zhao, Xi'an Jiaotong University
ICONE19-43167
BUBBLE-TYPE GAS ENTRAINMENT INTO LIQUID FROM FREE SURFACE BY VORTEX
Yasuo Koizumi, Shinshu University
ICONE19-43786
THERMAL HYDRAULIC TEST OF ADVANCED FUEL BUNDLE WITH SPECTRAL SHIFT ROD (SSR) FOR BWR - EFFECT OF THERMAL HYDRAULIC PARAMETERS ON STEADY STATE CHARACTERISTICS -
Takao Kondo, Hitachi-GE Nuclear Energy, Ltd.
ICONE19-43586
Effectiveness of natural circulation on molecular diffusion of two component gases in a stratified fluid layer
Tetsuaki Takeda, University of Yamanashi
ICONE19-43772
DROPLET DEPOSITION RATE IN VERTICAL ANNULAR TWO-PHASE FLOW
Pravin Sawant, Energy Research, Inc., Rockville, MD-20852, USA
Michitsugu Mori, Tokyo Electric Power Co., Inc.
Session 25 A-1 (9:00- 11:00)
Session Chair, Co-chair
Atsushi Ishikawa, IHI
Robin J. McCollum, Bechtel Marine Propulsion Inc.
TRK 11 Instrumentation & Controls
Track Chair: Kenji Urase, Hitachi-GE Nuclear Energy, Ltd.
Track Co-Chair: Bob Stakenborgh, ILD, Inc.
Track Co-Chair: Zhijian Zhang
Track Co-Chair: Hirohisa Satomi, Hitachi,Ltd.
ICONE19-43115
ASSESSMENT OF ADVANCED REACTOR CORE PROTECTION SYSTEM FOR PRESSURIZED WATER REACTOR
Wang-Kee In, KAERI
ICONE19-43169
VERIFICATION OF FPGA-BASED NPP I&C SYSTEMS: GENERAL APPROACH AND TECHNIQUES
Anton Andrashov, Centre for Safety Infrastructure-Oriented Research and Analysis
ICONE19-43216
ASSESSMENT OF MULTI-VERSION NPP I&C SYSTEMS SAFETY: METRIC-BASED APPROACH, TECHNIQUE AND TOOL
Viacheslav I. Duzhyi , Centre for Safety Infrastructure-Oriented Research and Analysis
ICONE19-43159
Conceptual Design of an FPGA-Based AMSAC System for Taiwan's Maanshan NPP
Jun-Jen Lu, National Tsing Hua University
ICONE19-43011
ROBUSTNESS OF NUCLEAR CORE ACTIVITY RECONSTRUCTION BY DATA ASSIMILATION
Bertrand BOURIQUET, CERFACS
ICONE19-43013
OPTIMAL DESIGN OF MEASUREMENT NETWORK FOR NEUTRONIC ACTIVITY FIELD RECONSTRUCTION BY DATA ASSIMILATION
Bertrand BOURIQUET, CERFACS
ICONE19-43461
RESEARCH ON THE OPTIMIZATION OF SAFETY INFORMATION AND CONTROL SYSTEM OF CPR1000 NPP
Ke Tan, CNPEC, Shenzhen, PRC
ICONE19-43003
REACTOR COOLANT FLOW CALCULATOR
Peter Hung, Westinghouse Electric Company LLC
ICONE19-43623
THE BACKUP OF MAIN CONTROL MEANS ANALYSIS AND APPLICATION IN HYH NPP
Huang Weijun, China Nuclear Power Design Co., LTD
ICONE19-43895
OPTIMUM INJECTION PRESSURE OF A CAVITATING JET ON INTRODUCTION OF COMPRESSIVE RESIDUAL STRESS INTO STAINLESS STEEL
Hitoshi Soyama, Tohoku University
Session 25 B-1 (9:00- 11:00)
Session Chair, Co-chair
Tetsuaki Takeda, University of YamanashiJoe Miller, EDA, Inc.
David L. Aumiller, Bechtel Marine Propulsion Inc.
TRK 12 Next Generation Systems
Track Chair: Ryodai Nakai, Japan Atomic Energy Agency
Track Co-Chair: Tetsuaki Takeda, University of Yamanashi
Track Co-Chair: Ryutaro Hino, Japan Atomic Energy Agency
Track Co-Chair: Huiping Cheng
Track Co-Chair: Glenn Harvel, University of Ontario Institute of Technology
Track Co-Chair: Toru Nakatsuka, Japan Atomic Energy Agency
ICONE19-43804
SAFETY CONSIDERATION IN CORE DESIGN OF KALIMER-600, METALLIC FUELED SFR
Moo-Hoon Bae, Korea Institute of Nuclear Safety (KINS)
ICONE19-43935
Development of a Helical-Coil Double Wall Tube Steam Generator for 4S Reactor
Yuko Kitajima, TOSHIBA Corporation
ICONE19-43807
SAFETY ASPECTS OF VERY HIGH TEMPERATURE REACTOR CORE DESIGN
Chang-Yong Jin, Korea Institute of Nuclear Safety (KINS)
ICONE19-43264
TIGHTLY COUPLED MULTIPHYSICS SIMULATIONS FOR PRISMATIC REACTORS
Hiroyuki Sato, Japan Atomic Energy Agency (JAEA)
ICONE19-43738
Research on Physical Characteristics of the First Core in the Pebble Bed High Temperature Gas-Cooled Reactor
Jingyu ZHANG, Tsinghua University (China)
ICONE19-43227
THE DYNAMIC MATHEMATIC SIMULATION MODEL OF STEAM GENERATOR FOR HTR-PM
Sui Zhe , INET, Tsinghua University (China)
ICONE19-43742
FLOWSHEET STUDY OF HI SEPARATION PROCESS FROM HI-H2O-I2 SOLUTION IN THE THERMOCHEMICAL HYDROGEN PRODUCTION IODINE-SULFUR (IS) PROCESS
Seiji Kasahara, Japan Atomic Energy Agency (JAEA)
ICONE19-43220
DEVELOPMENT OF HYDRAULIC ANALYSIS CODE FOR OPTIMIZING CERAMICS REACTORS
Atsuhiko Terada, Japan Atomic Energy Agency (JAEA)
ICONE19-43177
Experimental Study of Airflow-Mixture by Using PIV
Yu Kamiji , Japan Atomic Energy Agency (JAEA)
ICONE19-43459
ADS CORE DESIGN AND BURNUP ANALYSIS
Yongwei YANG, INET, Tsinghua University, China
ICONE19-43038
Response matrix method and its application to SCWR single channel stability analysis
Jiyun Zhao, Nanyang Technological University, China
ICONE19-43147
NUMERICAL ANALYSIS OF TURBULENT FLOW WITH HEAT TRANSFER IN A SQUARE DUCT WITH 45 DEGREE RIBS
Yuria Okagaki, Utsunomiya University
ICONE19-43563
Corrosion test of metallic materials in high temperature acidic environments of IS process
Nobuyuki Tanaka, Japan Atomic Energy Agency
Session 25 C-1 (9:00- 11:00)
Session Chair, Co-chair
Kazuhiko Yamamoto, Japan Atomic Power Company
Robert A. Wall, Bechtel Marine Propulsion Inc.
TRK 13 Fusion Engineering
Track Chair: Hiroshi Horiike, Osaka University
Track Co-Chair: Yican Wu, Institute of Plasma Physics, Chinese Academy of Sciences
Track Co-Chair: Igor Jovanovic, The Pennsylvania State University
Track Co-Chair: Kunugi Tomoaki, Kyoto University
Track Co-Chair: Akihiko Shimizu, Kyushu University
ICONE19-43944
FIRST NEUTRONICS ANALYSIS FOR ITER BIO-SHIELD EQUATORIAL PORT PLUG
Tong Qiang Dang, University of Science and Technology of China, China
ICONE19-43608
DIAGNOSTICS OF HIGH-SPEED LIQUID LITHIUM JET FOR IFMIF/EVEDA LITHIUM TEST LOOP
Takuji Kanemura , Japan Atomic Energy Agency (JAEA)
ICONE19-44185
Study on Surface Wave Characteristics of Free Surface Flow of Liquid Metal Lithium for IFMIF
Eiji Hoashi, Osaka University
ICONE19-43107
UPWINDING MESHFREE POINT COLLOCATION METHOD FOR UNSTEADY MAGNETOHYDRODYNAMIC FLOW AT HIGH HARTMANN NUMBERS
Zhao Liang, Xi'an Jiaotong University
TRK 15 Nuclear Education, Human Resources and Public Acceptance
Track Chair: Junko Ogawa, Tokyo City University
Track Co-Chair: Koji Okamoto, University of Tokyo
Track Co-Chair: Jay Kunze, Idaho State University
Track Co-Chair: Stephen Kidd, WNA
Track Co-Chair: Changxin Liu, Chinese Nuclear Society
Track Co-Chair: Kazuhiko Yamamoto, The Japan Atomic Power Company
ICONE19-43045
The Current State and Issues Regarding Communication from the Nuclear Energy Industry to the Mass Media in Japan
Tatsuro Tsuchida, The University of Tokyo
ICONE19-43270
PROGRESSION OF TECHNOLOGY EDUCATION FOR ATOMIC ENERGY ENGINEERING IN TSUYAMA NATIONAL COLLEGE OF TECHNOLOGY
T. Kobayashi, Tsuyama National College of Technology
ICONE19-43294
ANALYSIS AND EVALUATION FOR SOCIAL ACCEPTABILITY FOR UTILIZING NUCLEAR POWER IN CHINA
Ting XU, Tohoku University
ICONE19-43265
PUBLIC OFFERING SYSTEM OF RESEARCH AND DEVELOPMENT IDEAS IN JAPC
Yoshiyuki Nakayama, The Japan Atomic Power Company
Session 25 D-1 (9:00- 11:00)
Session Chair, Co-chair
Hideaki Monji, Tsukuba University
Wang Yongliang, Hefei Institutes of Physical Science, Chinese Academy of Sciences.
TRK 14 Reactor Physics, Neutronics and Transport Theory
Track Chair: Akio Yamamoto, Nagoya University
Track Co-Chair: Hideki Matsumoto, Mitsubishi Heavy Industries, Ltd./Reactor Core Engineering
Track Co-Chair: Hongchun Wu, Xi'an Jiaotong University
Track Co-Chair: Zafar Koreshi, Air University
ICONE19-43095
Development of BWR Transient Analysis Code TRACT
Norio Sakai , Toshiba Corporation
ICONE19-43911
THE SIMULATION ON THE RUNNING-IN PHASE OF THE HTR-10
Bing XIA , Institute of Nuclear and New Energy Technology (China)
ICONE19-43917
CHARACTERISTIC STATISTIC ALGORITHM (CSA) AND ITS APPLICATION ON LARGE PWR RELOADING DESIGN
Zhihong Liu, INET, Tsinghua University, China
ICONE19-43959
VERIFICATION OF JUPITER STANDARD ANALYSIS METHOD FOR UPGRADING JOYO MK-III CORE DESIGN AND MANAGEMENT
Shigetaka Maeda, Japan Atomic Energy Agency (JAEA)
ICONE19-43353
DEVELOPMENT AND VALIDATION OF BURNUP FUNCTION IN REACTOR MONTE CARLO RMC
Ding SHE, Tsinghua University (China)
ICONE19-43067
Application of data mining in three-dimensional space time reactor model
Botao Jiang, Xi'an Jiaotong University (China)
ICONE19-43209
SPATIALLY DEPENDENT GRAY RESONANCE SHIELDING METHOD FOR GENERATING RADIAL POWER PROFILES WITHIN PELLET
Hiroki Koike, Mitsubishi Heavy Industries, Ltd.
ICONE19-43188
Development of a New Lattice Physics Code GALAXY-H for Hexagonal Geometries
Yohei Kamiyama, Mitsubishi Heavy Industries, Ltd.
