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図書
1. Plant Operations and maintenance, major component reliability and materials issues : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000 (v. 1)
conference organized and sponsored by The American Society of Mechanical Engineers, ASME, Societeé Française d'Energie Nucléaire, SFEN, Japan Society of mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, ... [et.al.]
出版情報: New York : American Society of Mechanical Engineers, c2000  xvii, 904p. ; 28 cm
シリーズ名: Proceedings of the 8th International Conference on Nuclear Engineering 2000 : ICONE-8, Baltimore, Maryland, April 2-6, 2000 / conference organiaed and sponsored by American Society of Mechanical Engineers, ASME, Societé Française d'Energie Nucléaire, SFEN, Japan Society of Mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, Electric Power Research Institute, EPRI, International Atomic Energy Agency, IAEA ; v. 1
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Plant Operations and Maintenance
Operational Experiences/Root Cause Failure Analyses
ICONE8-8032 Experimental Study of Impact/Sliding Wear of Rod Cluster Control Assemblies of PWR Nuclear Power Plants / D. Moinereau ; D. Hersant ; A. Lina ; M. Zbinden
ICONE8-8223 Application of CrN Ceramics Coating for Valve Seats to Reduce Cobalt Dissolution / Y. Iwata ; K. Takeshima ; K. Oosumi ; Y. Chiba
ICONE8-8226 Automatic, Multi-Constrained Methodology Compensating Venturi Corrosion Effects at STP Nuclear Operating Company Units 1 and 2: Algorithms and Implementation Summary / E. J. Kee ; J. Vuong ; S. E. Slavichak ; D. C. Sicking ; R. M. Ulanday
ICONE8-8551 What Caused the Failures of the Westinghouse Type AR Relays / T. P. Vassallo, Jr. ; K. J. Letourneau ; O. J. Van Der Schijff
ICONE8-8580 Environmentally Assisted Stress Corrosion Cracking Failure of 410 Stainless Steel Valve Stems in RHR Water / D. Kalmanovitch ; W. McBrine ; L. E. Willertz ; B. M. Swoyer
ICONE8-8615 Leakage From CVCS Pipe of Regenerative Heat Exchanger Induced by High-Cycle Thermal Fatigue at Tsuruga Nuclear Power Station Unit 2 / T. Hoshino ; T. Aoki ; T. Ueno ; Y. Kutomi
Operations and Maintenance Issues
ICONE8-8120 Olkiluoto 1 and 2: Safety Practices During Planned Outages / M. Mustonen ; S. Koski ; M. Kosonen ; R. Himanen ; M. Hakola
ICONE8-8139 Partial Discharge On-Line Monitoring in Switchgears and Bus Ducts of Nuclear Power Plants / Z. Berler ; I. Blokhintsev ; A. Golubev ; A. Romashkov ; V. Rashkes ; A. Seliber
ICONE8-8251 Experimental and Analytical Study on Thermal Displacement Characteristics of Cooling System Applied to Floating Support Unit / S. Hanawa ; M. Ishihara ; Y. Tachibana ; H. Koikegami
ICONE8-8477 Simplified Head Assembly Design and Implementation / M. Ball ; A. W. Harkness
ICONE8-8508 Development of Large Capacity Main Steam Safety Relief Valve (SRVS) System Design / K. Ando ; S. Yamanari ; S. Kinoshita ; K. Takasaki
ICONE8-8665 Reducing Outage Time With Use of Temporary Reactor Head / J. C. Hedtke
Improving Efficiency and Reducing Costs of O and M
ICONE8-8026 Maintenance and Radiation Protection Policy for EPR / C. Degrave ; R. Griedl ; A. Gobel ; M. Rudiger
ICONE8-8052 Real Time Water Chemistry Monitoring and Diagnostic System / T. M. Gaudreau ; P. J. Millett
ICONE8-8083 Reconciliation of Process Data in Nuclear Power Plants (NPPs) / E. Grauf ; J. Jansky ; M. Langenstein
ICONE8-8140 On-Line Monitoring of Large Power Transformers in Nuclear Power Plants: The Way to Increase Reliability and to Reduce Maintenance Cost / V. Tsvetkov ; V. Sokolov
ICONE8-8453 Development of a Portable Reactor Noise Analysis System (RENAS) for the Vibration Monitoring of Reactor Internals / J. Park ; H.-R. Kim ; H.-Y. Nam ; S.-T. Hwang ; G.-Y. Park
Life Cycle Management
ICONE8-8364 Nuclear Property Insurance Experience of an Aging Global Nuclear Industry / W. G. Wendland
ICONE8-8379 Life Cycle Prediction for Composites Subjected to Low Cycle Fatigue / V. M. Harik ; T. A. Bogetti ; B. K. Fink ; J. R. Klinger ; A. Paesano ; J. W. Gillespie, Jr.
ICONE8-8381 Life Cycle Management Planning for Important Nuclear Power Plant Systems, Structures, and Components / M. Arey ; A. Smith ; S. Hunt ; G. Sliter ; F. Gregor
ICONE8-8441 Development and Application of Laser Peening System to Prevent Stress Corrosion Cracking of Reactor Core Shroud / Y. Sano ; M. Kimura ; K. Sato ; M. Obata ; A. Sudo ; Y. Hamamoto ; S. Shima ; Y. Ichikawa ; H. Yamazaki ; M. Naruse ; S. Hida ; T. Watanabe ; Y. Ohno
ICONE8-8736 Integrated Thermal-Hydraulic and Economic Modeling / R. E. Berger
Risk Informed/Risk Based Maintenance, Monitoring and Inspection
ICONE8-8006 A Proposal to Solve the Millennium Type of Problems Using Probabilistic Risk Assessment Method in Nuclear Installation and Beyond / R. R. Pahladsingh
ICONE8-8141 Optimization of SG Tube Maintenance Strategies Using Probabilistic Approach / M. Sagisaka ; Y. Isobe ; S. Yoshimura ; G. Yagawa
ICONE8-8569 Integrated Maintenance Rule Assessments Using the Safety Monitor / M. A. Phillips ; D. M. Jones ; J. A. Julius
OandM Management: Training and Process Improvement
ICONE8-8015 Outsourcing Nuclear Engineering Management and the Performance Linkage / H. Hoelscher ; L. Ramme
ICONE8-8046 A Systematic Approach for Continuing Engineer Training / A. C. Taylor ; P. Higgins ; G. Wardlaw
ICONE8-8306 Development of an Engineering Knowledge Management System for Nuclear Power Plants / H. Seki ; T. Kasahara ; Y. Oota
ICONE8-8375 Development and Application of a New Electronic Personal Dosimeter / M. Fujita ; K. Taniguchi ; K. Muramatsu ; S. Ishikawa ; H. Yamakawa
ICONE8-8526 Development of Leak Detection System for Piping Using High-Temperature Resistant Microphone: (1)--Development of System / H. Mochizuki ; H. Takeda ; Y. Kasai ; F. Nakamura ; Y. Morishita ; B. Strelkov ; S. Shimanskiy ; V. Lebedev ; V. Vanukov
ICONE8-8527 Development of Leak Detection System for Piping Using High-Temperature Resistant Microphone: (2)--Multi-Channel Test / S. Strelkov ; A. Ananyev ; V. Picos ; V. Ljubishkin
Performance Indicators/Performance Measures
ICONE8-8057 Performance Indicators in the Spanish Nuclear Regulatory Council (CSN) / M. Marono ; R. Sola ; J. Zarzuela
ICONE8-8262 Cofrentes NPP: Indicators to Monitor Operational Safety Performance. Two Examples: Deterministic Shutdown Risk/Probabilistic Risk Monitoring at Power / J. M. Palomo ; F. C. Calduch
ICONE8-8279 Evaluation of Performance Characteristics for Korean Standard Nuclear Power Plants / J. H. Choi ; S. W. Sohn ; I. H. Song ; J. J. Sohn ; J. T. Seo
ICONE8-8632 EnergiTools: A Power Plant Performance Monitoring and Diagnosis Tool / P. V. Ancion ; R. Bastien ; K. Ringdahl
Plant Power Uprating Issues and Experiences and Control Systems Upgrades
ICONE8-8028 WWER Control Systems Upgrades (Safety Aspects) / M. A. Yastrebenetsky ; V. N. Vasilchenko
ICONE8-8329 Development and Validation Process of the Advanced Main Control Board for Next Japanese PWR Plants / K. Ito ; M. Yokoyama ; M. Imase
ICONE8-8415 Measurement of BWR Reactor Physics Characteristics Using Digital Reactivity Meter / M. Nakano ; Y. Komano ; T. Anegawa ; T. Hara ; H. Tanaka ; E. Saji
ICONE8-8421 Development of a Dual Redundant Digital Control System With Fault-Tolerance / S. H. Seong ; Y. S. Suh ; D. H. Kim ; S. Hur ; I. S. Koo
ICONE8-8575 The Basis for a 1% Power Increase: LEFM3 Technology / D. Augensetin ; J. Regan
ICONE8-8663 Improved Methods for On-Line Sensor Calibration Verification / J. W. Hines ; A. V. Gribok ; J. Attien ; R. E. Uhrig
Plant Systems Maintenance and Reliability Improvements
ICONE8-8159 Availability, Maintenance and Feedback: Factors in the Competitiveness of Future Nuclear Power Plants / C. Meuwisse ; H. Chardonnal ; M. Martin-Onraet
ICONE8-8401 Development of Hybrid Hydrogen Control System / H. Nakakura ; T. Gora
ICONE8-8416 Improvement of RCM Method Based on Maintenance Experience / M. Watanabe ; N. Shinkai ; Y. Naruse ; Y. Ohta ; J. Dozier
ICONE8-8485 Robust Hydrogen Sensor for the Leningrad Nuclear Power Plant / D. L. Dunn
ICONE8-8532 Development and Verification of High Speed and Automatic Fuel Handling System / H. Yamaguchi ; S. Ueda ; S. Nakamura ; T. Maeda
Fire Protection
ICONE8-8172 Nuclear Power Fire Incident Database Results / T. K. Furlong
ICONE8-8270 International Guidelines for the Fire Protection of Nuclear Power Plants / E. Dressler
ICONE8-8668 Industry Plans for Fire Protection Assessment at Nuclear Plants / F. Emerson
ICONE8-8669 An Industry Approach to Resolving Fire-Induced Circuit Failures / T. Gorman ; R. Kassawara
Major Component Reliability and Materials Issues
Steam Generator Tube Integrity and Inspection
ICONE8-8041 A Probabilistic Evaluation of the Risk of SG Tube Rupture Using a Statistical Modelling of the Degradation Behaviour / V. Durbec ; T. Riffard ; P. Lemaire
ICONE8-8200 Structural Integrity of Flawed Steam Generator Tubes: Experimental Facilities and Test Results / K. E. Kasza ; S. Majumdar ; D. R. Diercks
ICONE8-8201 Testing and Analysis of Structural Integrity of Electrosleeved Tubes Under Severe Accident Transients
ICONE8-8202 Status of Argonne Steam Generator Mock-Up NDE Round Robin / D. S. Kupperman ; S. Bakhtiari ; J. Muscara
ICONE8-8474 Use of Empirically Based Corrosion Model to Aid Steam Generator Life Management / P. Angell ; P. V. Balakrishnan ; C. W. Turner
ICONE8-8537 PWR Steam Generator Bundle Wrapper Degradations: Background, Analysis and Solutions / J. P. Gauchet ; F. Munoz ; E. Molinie ; M. Petit
ICONE8-8538 PWR Steam Generator Bundle Wrapper Degradations: Maintenance and In-Service Surveillance/Feedback Experience / M. Stindel ; P. Homo
ICONE8-8641 CANDU Reactor Plant Life Extension: Steam Generator Considerations / R. L. Tapping ; J. Nickerson ; N. Subash ; K. D. Verma
ICONE8-8664 Simulation of Intergranular Cracking in 1600 SG Tubes Using Voronoi Tessellation / L. Cizelj ; H. Riesch-Oppermann
Aging and Modeling of Component Aging, Including Corrosion of Metals and Welds (Passivation, Passive Films)
ICONE8-8230 Combination Between a Finite Element Code and a Probabilistic Code to Estimate the Failure Probability of PWR Pressure Vessels / V. Venturini ; I. Debost-Eymard ; E. Meister ; G. Nicolas ; M. Persoz
ICONE8-8288 Deposition of Chromium Coatings by Pack-Cementation Onto the Nickel-Base Superalloy Inconel 690 / M. Vilasi ; T. Belmonte ; C. Rives ; T. Czerwiec ; H. Michel
ICONE8-8301 Fracture Toughness Characterization of Type 304 Stainless Steel Irradiated in the Halden Reactor / O. K. Chopra ; E. E. Gruber ; W. J. Shack
ICONE8-8356 Development of Evaporators Made of Ti-5% Ta Alloy and Zr: Endurance Test by Mock-Up Unit / M. Takeuchi ; T. Takata ; T. Koizumi ; A. Aoshima
Use of Diagnostic Tools Appropriate for Elastic/Plastic Deformation in Nuclear Reactor Components and Other Devices
ICONE8-8287 Surface Passivation of Inconel 690 Using Gas-Phase and Post-Discharge Oxidation / F. Belnet ; O. Kerrec
ICONE8-8517 Monte Carlo Simulation on Ultrasonic Wave Propagation in Oxidized Graphite Components in the HTGR / T. Shibata
ICONE8-8785 The Growth Rate and Plastic Zone Size Variations of a Fatigue Crack Grown in a Tensile Residual Stress Field / Y. Prawoto ; R. A. Winholtz
ICONE8-8815 Determining Strain/Stress Profiles in PIGMA (Pressurized Inert Gas Metal Arc) Weld Between Beryllium Metal Rings by Neutron Diffraction and Comparing Results Obtained From Finite Element Analysis / R. Varma ; D. W. Brown ; F. M. Guerra ; M. Bourke ; P. Burghardt ; M. D. Garcia
New Tools and Technologies for Repair of Nuclear Plant Structures
ICONE8-8022 Development of Reconstitution Technology for Surveillance Specimen / S. Hatano ; S. Kataoka ; T. Otsuka ; Y. Oka ; K. Taguchi ; M. Yamamoto
ICONE8-8151 YAG Laser Welding Certification Test Results in Underwater Environment / T. Kojima ; S. Satoh ; T. Kochi ; K. Ohwaki ; I. Morita
ICONE8-8152 Development of YAG Laser Cladding Technology to Heat Exchanger Flange / K. Nezaki ; K. Ninomiya
ICONE8-8311 Application of Water Jet Peening Technology to BWR Core Shroud for IGSCC Mitigation / W. Sagawa ; H. Anzai ; K. Hirano ; T. Ishida ; H. Gotoh
ICONE8-8755 Adaptive Volume Controlled Expansion of Alloy 800 Sleeving / Y. Sun ; Z. Gan ; E. F. Lamoureux
BWR Vessel and Internals Project
ICONE8-8127 Is BWR Internals Replacement Cost-Effective? / H. Kornfeldt
ICONE8-8259 Alternate Methods for Evaluating Shroud Cracking Using Linear Elastic Fracture Mechanics Techniques / R. E. Ciemiewicz ; R. J. McCall ; D. L. Schmidt ; M. L. Herrera ; R. A. Mattson
ICONE8-8260 Alternate Core Plate Rim Hold-Down Bolt Evaluation / P. S. Gore ; J. W. Langdon ; W. B. Wilton ; L. Yemma ; G. L. Stevens
ICONE8-8261 Jet Pump Flaw Evaluation Procedures / D. M. Swann
ICONE8-8282 Vertical Weld Repair in a Boiling Water Reactor Core Shroud / H. W. McCurdy ; T. J. Haertel
ICONE8-8322 Technical Challenges and Solutions: Activities of the BWRVIP Inspection Committee / G. Selby ; C. Larsen
ICONE8-8494 Application of Probabilistic Fracture Mechanics Methods to Evaluate Boiling Water Reactor Pressure Vessel Integrity / P. C. Riccardella ; S. S. Tang
ICONE8-8609 Overview of BWRVIP Mitigation Committee Activities / J. A. Wilson ; R. S. Pathania
ICONE8-8716 Determination of 3-D Neutron and Gamma Fields at BWR Core Shroud / V. N. Kucukboyaci ; A. Haghighat
LWR Materials Issues
ICONE8-8094 Prediction of Light Water Reactor Contamination Using the PACTOLE Code / D. Tarabelli ; S. Anthoni ; P. Menut
ICONE8-8229 Modeling of VVER Light-Water Reactors Activity Buildup / K. Dinov ; I. Dobrevski ; N. Zaharieva
ICONE8-8300 Effects of Light Water Reactor Coolant Environments on Fatigue Crack Initiation in Piping and Pressure Vessel Steels
ICONE8-8472 Resolution of GSI-190, "Fatigue Evaluation of Metal Components for 60-Year Plant Life" / S. K. Shaukat ; D. N. Kalinousky
ICONE8-8572 An Evaluation of Flaw Tolerance Procedures Used for Component Fatigue Life Qualification / R. G. Carter ; M. E. Mayfield ; S. R. Gosselin ; F. A. Simonen
Materials Aging Issues
ICONE8-8386 Non-Destructive Analysis of Hydrogen in Nuclear Power Plant Materials / W. H. Miller ; M. P. Popovici ; R. L. Groza
ICONE8-8493 An Electrochemical Corrosion Analysis of Stainless Steel Plutonium Storage Containers / T. DeFee ; H. Wheat ; S. Landsberger
Qinshan Reactor Internals Recovery Project
ICONE8-8059 Qinshan 1 Reactor Internals Recovery Project / M. Mahlab
ICONE8-8060 CFD Analysis of Qinshan 1 Reactor Vessel Internals Below Fuel Core / N. Singleton ; V. Gurumoorthy ; J. P. Henning ; T. Valachovic ; A. Harkness ; Z. Ming
ICONE8-8061 Vibration Assessment of the Qinshan 1 Internals Replacement Structures / C. Yu ; N. R. Singleton ; W. D. Yao
ICONE8-8062 Replacement Component Design for Qinshan Unit 1 / D. E. Ekeroth ; J. C. Matarzzo ; D. H. Roarty
ICONE8-8063 Qinshan 1: Inverting/Uprighting the Lower Internals Assembly / D. E. Seeger, Jr. ; R. G. Patel ; J. Matusz ; R. E. Meuschke ; T. Qian
ICONE8-8064 Finite Element Stress Analyses of the Lower Internals and Upender Assembly / A. Danay ; M. A. Mahlab ; D. E. Boyle ; A. T. Paterson
ICONE8-8065 Qinshan 1: Field Implementation of Reactor Internals Modifications / M. S. McGough ; J. J. Jesko, Jr. ; Y. Wong
ICONE8-8066 Qinshan 1: Dimensional Measurements on the Lower Reactor Internals and Reactor Vessel / R. A. Kucera ; J. T. Polidora ; P. L. Strauch
ICONE8-8068 Reactor Vessel Cladding Damage Analysis / W. Bamford ; K. R. Hsu
ICONE8-8577 Qinshan 1: Reactor Vessel Cladding Damage Replication and Measurement / C. D. Webb ; J. C. Matarazzo ; C. C. Kim ; T. Thompson ; S. Lindhorst
Stress Corrosion Cracking in Low-Pressure Turbine Rotors
ICONE8-8111 Improvements in the Manufacture and Stress Corrosion Crack Susceptibility of Low-Pressure Turbine Rotors / H. Itoh ; A. Matsuo ; T. Momoo
ICONE8-8112 Residual Life Prediction Controlled by SCC Initiation in 3.5 NiCrMoV Turbine Disc Steel Under Field Turbine Conditions / T. Sakaguchi
ICONE8-8113 SCC Susceptibility of 3.5 NiCrMoV Steel in an Actual Low-Pressure Turbine Environment / S. Tsukamoto
ICONE8-8114 Monitoring of the Effect by Boron Soaking on SCC in 3.5 NiCrMoV Turbine Disc Steel Over a 12-Year Period / H. Matsumura
Author Index
Plant Operations and Maintenance
Operational Experiences/Root Cause Failure Analyses
ICONE8-8032 Experimental Study of Impact/Sliding Wear of Rod Cluster Control Assemblies of PWR Nuclear Power Plants / D. Moinereau ; D. Hersant ; A. Lina ; M. Zbinden
2.

図書
図書
2. Structural integrity, dynamic behavior, and seismic design, next generation systems : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000 (v. 2)
conference organized and sponsored by The American Society of Mechanical Engineers, ASME, Societeé Française d'Energie Nucléaire, SFEN, Japan Society of mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, ... [et.al.]
出版情報: New York : American Society of Mechanical Engineers, c2000  xvi, 861p. ; 28 cm
シリーズ名: Proceedings of the 8th International Conference on Nuclear Engineering 2000 : ICONE-8, Baltimore, Maryland, April 2-6, 2000 / conference organiaed and sponsored by American Society of Mechanical Engineers, ASME, Societé Française d'Energie Nucléaire, SFEN, Japan Society of Mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, Electric Power Research Institute, EPRI, International Atomic Energy Agency, IAEA ; v. 2
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3.

図書
図書
3. License renewal, life extention, decommissioning, and decontamination, basic nuclear engineering advances : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000 (v. 3)
conference organized and sponsored by The American Society of Mechanical Engineers, ASME, Societeé Française d'Energie Nucléaire, SFEN, Japan Society of mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, ... [et.al.]
出版情報: New York : American Society of Mechanical Engineers, c2000  xv, 676p. ; 28 cm
シリーズ名: Proceedings of the 8th International Conference on Nuclear Engineering 2000 : ICONE-8, Baltimore, Maryland, April 2-6, 2000 / conference organiaed and sponsored by American Society of Mechanical Engineers, ASME, Societé Française d'Energie Nucléaire, SFEN, Japan Society of Mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, Electric Power Research Institute, EPRI, International Atomic Energy Agency, IAEA ; v. 3
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目次情報: 続きを見る
License Renewal, Life Extension, Decommissioning, and Decontamination
DandD Technology Demonstration in a Non-Radioactive Environment
ICONE8-8429 Development of YAG Laser Remote Cutting System for Decommissioning / K. Okimura ; H. Kono ; O. Kohanawa ; T. Ishide ; Y. Nagura ; S. Tsubota
ICONE8-8687 OXY-Gasoline Cutting Torch Speeds Nuclear DandD / M. Heft
ICONE8-8690 Deactivation and Decommissioning Technology Assessment Program / S. Madaris ; C. Zhang ; C. Aponte ; M. Allen
DandD Technology Demonstration in Non-Reactor Facilities
ICONE8-8652 In-Situ Site Characterization Technologies Demonstrated at the INEEL in Decommissioning Projects / K. C. Wright ; R. H. Meservey ; L. Whitmill
ICONE8-8661 Keys to Successful DandD Technology Deployments at the INEEL / A.-M. Smith ; H. D. Shoemaker
ICONE8-8706 Mound Tritium DandD Large-Scale Demonstration and Deployment Project / D. R. Krause ; J. O. Johnson ; M. Mintz
DandD Experience at Reactor Facilities
ICONE8-8097 The Big Rock Point Sampling and Condition Assessment Project / F. Polaski ; J. Rang ; J. Carey ; D. F. Lehnert ; F. E. Gregor
ICONE8-8336 The RPV Dismantling of the BR3 PWR Pilot Project / J. Dadoumont ; V. Massaut ; M. Klein ; Y. Demeulemeester
ICONE8-8749 The Technical Development of Graphite Waste Treatment / S. Saishu ; T. Inoue
Facility Aging and Equipment Replacement
ICONE8-8021 Assessment of Cable Aging Using Condition Monitoring Techniques / E. J. Grove ; R. Lofaro ; P. Soo ; M. Villaran ; F. Hsu
ICONE8-8192 Strategy Adopted for the Life Extension of Heavy Water Plants in India: Piping Analysis / R. Mishra ; R. S. Soni ; H. S. Kushwaha ; V. Venkat Raj
ICONE8-8264 Neutron Flux Enhancement Test Vehicle for Material Embrittlement Acceleration Tests / G. S. Chang ; R. G. Ambrosek ; J. W. Rogers ; F. W. Ingram
ICONE8-8334 A Durability Analysis of the CASCAD Facility Based on Feedback Obtained After 10 Years of Operation / D. Canas ; R. Samoel ; P. Battesti
ICONE8-8337 Non-Destructive Monitoring of the Thermal Aging of Cast Duplex Stainless Steels Using Thermopower Measurements / J.-F. Coste ; Y. Kawaguchi
ICONE8-8345 Age-Related Degradation of Structures and Passive Components at Nuclear Power Plants / J. I. Braverman ; C. H. Hofmayer ; S. Shteyngart ; R. J. Morante ; T. Y. Chang
ICONE8-8557 PRA in Support of License Renewal / E. Krantz ; J. Leary
ICONE8-8628 Maintenance Program for Containment Vessel With Crane Wall / Y. Horikawa ; K. Matsueda ; Y. Nishida
Basic Nuclear Engineering Advances
Spallation Neutron Sources
ICONE8-8457 Recent Progress in Design Study of Japanese Spallation Neutron Source / N. Watanabe ; M. Teshigawara ; T. Kai ; M. Harada ; H. Sakata ; Y. Ikeda ; M. Kaminaga ; R. Hino ; Y. Oyama
ICONE8-8464 SNS Remote Handling and the Target Test Facility / P. T. Spampinato ; T. W. Burgess ; V. B. Graves ; T. L. Ray ; M. J. Rennich ; S. L. Schrock
ICONE8-8465 The European Spallation Neutron Source Project (ESS) / G. S. Bauer
ICONE8-8467 The Swiss Spallation Neutron Source SINQ
ICONE8-8458 Developments in the Design of Moderators for the Spallation Neutron Source / A. T. Lucas ; J. A. Crabtree
ICONE8-8611 The Lujan Center: A Pulsed Spallation Neutron Source at Los Alamos / G. J. Russell ; P. D. Ferguson ; E. J. Pitcher
ICONE8-8657 Design Description of the Bulk Shielding for the Spallation Neutron Source Target Facility / K. K. Chipley
ICONE8-8662 Moderator Optimization for the Spallation Neutron Facility / L. A. Charlton ; B. D. Murphy
Accelerator Driven Transmutation Technologies
ICONE8-8136 Fluence Limit Calculations for 304 Stainless Steel in Accelerator Driven Plutonium Conversion Applications / J. J. Park ; J. J. Buksa ; M. G. Houts ; E. D. Arthur
ICONE8-8245 A Technique for Dynamic Corrosion Testing in Liquid Lead Alloys / E. P. Loewen ; C. B. Davis ; P. E. MacDonald
ICONE8-8376 Thermal and Fast Spectrum Molten Salt ADS for Pu and MA Management / M. Valade ; G. Ritter ; M. Delpech ; M. Salvatores
ICONE8-8385 Molten Lead Enriched With Isotope Pb-206 as a Low-Activation Coolant for Emerging Nuclear Power Systems / G. L. Khorasanov ; A. P. Ivanov ; A. I. Blokhin ; A. Y. Konobeyev ; M. V. Mikhailyukova ; A. A. Glazkov ; A. D. Koljaskin
ICONE8-8500 Converging Beam Neutron Source for Driving a Subcritical Fission Reactor / G. H. Miley ; T. H. Bauer ; J. Nadler
ICONE8-8507 Design and Construction of Pb-Bi Corrosion Test Loop and Test Plan / M. Takahashi ; N. Sawada ; H. Sekimoto ; M. Kotaka ; T. Yano ; S. Uchida ; T. Takahashi ; K. Hata ; T. Suzuki
ICONE8-8555 Control Issues in Accelerator-Driven Subcritical System Design / P. Sullivan ; R. A. Rydin
Proliferation Resistance Reactor Designs
ICONE8-8014 Performance Modeling of Metallic and Nitride Fuels in Advanced Lead-Bismuth Cooled Fast Reactors / K. D. Weaver ; J. S. Herring
ICONE8-8072 Multipurposed Reactor Module SVBR-75/100 / A. V. Zrodnikov ; V. I. Chitaykin ; B. F. Gromov ; O. G. Grigoriev ; A. V. Dedoul ; G. I. Toshinsky ; Y. G. Dragunov ; V. S. Stepanov
ICONE8-8145 An Advanced Modular HLMC Reactor Concept Featuring Economy, Safety, and Proliferation Resistance / B. W. Spencer ; R. N. Hill ; D. C. Wade ; D. J. Hill ; J. J. Sienicki ; H. S. Khalil ; J. E. Cahalan ; M. T. Farmer ; V. A. Maroni ; L. Leibowitz
ICONE8-8315 The NILUS Concept: Safety and Economy Through Simplicity / C. Lombardi ; M. E. Ricotti ; R. Vigano ; L. Mezzera ; L. Oriani ; S. Romanova ; A. Tecci ; L. Corleto ; C. De Masi
ICONE8-8339 Novel, Integrated Reactor/Energy Conversion System Concept / D. V. Paramonov ; M. D. Carelli
ICONE8-8366 A Study on Non-Proliferative, Retrofittable PWR Fuel / Y. Katagiri ; Y. Yamane ; A. Yamamoto
ICONE8-8377 A Concept of a Gas-Cooled Particle-Bed Fast Reactor With Nitride Fuel / O. Koberl ; J. Tommasi ; F. Varaine
ICONE8-8447 IRIS, The International Reactor of the Future / C. V. Lombardi ; N. E. Todreas ; E. Greenspan ; J. Vujic ; R. Yamazaki ; K. Yamamoto ; A. Nagano ; G. L. Fiorini ; P. Dumaz ; T. Abram ; H. Ninokata
ICONE8-8720 Criteria for the Reactors of 2020 / S. Ion ; K. Hesketh
ICONE8-8750 The Encapsulated Nuclear Reactor Heat Source Reactor Concept / H. Shimada ; L. Conway ; N. W. Brown ; Q. Hossain
Advances in Nuclear Non-Destructive Analysis Technique
ICONE8-8035 Modeling of a Lead Spectrometer for the Assay of High Fissile Content Mixed Oxide Fuel / N. M. Abdurrahman ; L. E. Smith
ICONE8-8247 Spent Fuel Coincidence Counter: Determining the Fissile Content of Spent Fuel / P. Staples ; J. P. Lestone ; J. K. Sprinkle, Jr.
ICONE8-8302 Non-Destructive Analysis Using the Multi-Detector Analysis System / E. L. Reber ; J. D. Cole ; R. Aryaeinejad ; M. W. Drigert ; J. K. Jewell
ICONE8-8579 Selected Nondestructive Evaluation Applications of Thermal Neutron Imaging / Y. G. Jo ; M. A. Abdelrahman
Advances in Nuclear Instrumentation and Measurement Technologies
ICONE8-8076 Reliable Wireless Data Acquisition and Control Within Nuclear Hot Cell Facilities / J. L. Kurtz ; J. M. Cowdery ; J. S. Tulenko ; D. Schoenfeld ; S. Henderson ; R. Stewart ; M. Inskeep
ICONE8-8110 Development of Coated Gallium Arsenide Neutron Detectors / R. T. Klann ; D. S. McGregor
ICONE8-8414 Ionization Chamber for Measurement of the High Dose Rates / R. Nishiura ; H. Nishizawa ; T. Hirano
ICONE8-8692 Study of the Application of Ultrasonic Flow Meter to the ABWR Feedwater Flow Meter / T. Masuda ; K. Ichikawa ; N. Taoi ; K. Hara ; M. Yasuda ; K. Hiratsuka ; T. Yudate ; K. Kikunaga
ICONE8-8693 Recent Experiences on BWR Primary Containment Vessel Optic Temperature Monitoring System / T. Asano ; H. Furuuchi ; E. Kobayashi
Advances in Nuclear Systems Design and Analysis
ICONE8-8040 PWR Fuel Management Using Artificial Neural Networks / J.-M. Martinez ; S. Noceir ; H.-I. Wong
ICONE8-8249 Development and Results of a First Generation Least Expensive Approach to Fission: Module Tests and Results / M. Houts ; M. Van Dyke ; T. Godfroy ; R. Dickens ; K. Pedersen ; C. Dobson ; B. Reid ; J. T. Sena ; J. Martin
ICONE8-8267 Whole-Core Neutron Transport Calculations Without Cross Section Homogenization / M. A. Smith ; N. Tsoulfanidis ; E. E. Lewis ; G. Palmiotti ; T. A. Taiwo
ICONE8-8501 Two-Dimensional Nuclear Design Optimization Capability / Y. Karni ; D. Regev
ICONE8-8554 Recent Advances in Reactor Physics Standards / D. Cokinos
ICONE8-8637 Spectral Approximations for Some Linear Transport Problems / R. Panta Pazos ; M. Tullio de Vilhena
Health Effects of Low Level Radiation: Part A--Radiation Health Effects, Science
ICONE8-8787 Review of Cancer Risk in Animals Exposed to Low Doses of lonising Radiation / P. Duport
ICONE8-8788 Radiobiology Deceptions Reject Health / T. D. Luckey
ICONE8-8789 Low Dose Radiation Immunotherapy of Cancer / M. Pollycove
ICONE8-8790 Beneficial Radiation and Regulations / Z. Jaworowski
Health Effects of Low Level Radiation: Part B--Radiation Health Effects, Current Programs
ICONE8-8791 Let's Stop Regulating Harmless Low-Level Radiation / T. Rockwell
ICONE8-8794 Radiation Health Effects Research Programs Supported by Japanese Nuclear Utilities / M. Kaneko
Nuclear Engineering Education Research
ICONE8-8018 Development of Liquid-Vapor Core Reactors With MHD Generator for Space Power and Propulsion Applications / S. Anghaie
ICONE8-8098 Validation of a Point Reactor Model for Global Xenon Estimation / H. Jin ; M. Gadioli ; P. Wang ; T. Aldemir ; D. W. Miller ; J. W. Talnagi, Jr.
ICONE8-8118 Analytical and Numerical Solutions of Generalized Fokker-Planck Equations / A. K. Prinja ; F. Gleicher ; G. Dunham ; G. C. Pomraning
ICONE8-8250 Redesign of PUR-1 Core Using RELAP5 and MCNP / M. Bartel ; B. Wilson ; M. Miller
ICONE8-8263 Modeling of a Constant-Temperature Power Detector / T. D. Radcliff ; A. C. Kauffman
ICONE8-8319 Study of Second Phase Particles in Zr Alloys Using the Advanced Photon Source at Argonne National Laboratory / K. T. Erwin ; O. Delaire ; A. T. Motta ; R. C. Birtcher ; Y. S. Chu ; D. C. Mancini
ICONE8-8320 Study of Alloying Elements in the Zr Matrix of Zircaloy-4 and ZIRLO Using the Advanced Photon Source at Argonne / J. M. Maser ; B. Lai
ICONE8-8338 Gas Phase Chemical Reactions of Fission Products Using the Gas Jet Technique / E. Tratras Contis ; K. Rengan ; H. C. Griffin
ICONE8-8635 Three-Dimensional Study of Single Bubble Dynamics and the Surrounding Flow Field in a Small Diameter Pipe by Using Particle Tracking Velocimetry / J. Ortiz Villafuerte ; W. D. Schmidl ; Y. A. Hassan
ICONE8-8827 Bulk GaAs-Based Neutron Detectors for Spent Fuel Analysis / J. T. Lindsay ; Y.-H. Yang ; J. C. Lee
Alternate Nuclear Systems Based on Non-Standard Reactions
ICONE8-8095 Proton-Boron Colliding Beams for Nuclear Fusion / A. G. Ruggiero
ICONE8-8194 Evolution of IEC Fusion via Commercial FusionStar Opportunities / J. Sved
ICONE8-8571 Experimental Status and Potential Applications of a Thin-Film Low Energy Nuclear Reaction (LENR) Power Cell / G. Selvaggi ; A. Tate ; M. Okuniewski ; M. J. Williams ; D. Chicea
ICONE8-8660 The p-[superscript 11]B Colliding Beam Fusion Reactor / H. J. Monkhorst ; A. Qerushi ; N. Rostoker ; M. Binderbauer
ICONE8-8688 An Innovative Accelerator-Driven Inertial Electrostatic Confinement Device Using Converging Ion Beams / R. A. Wigeland
Author Index
License Renewal, Life Extension, Decommissioning, and Decontamination
DandD Technology Demonstration in a Non-Radioactive Environment
ICONE8-8429 Development of YAG Laser Remote Cutting System for Decommissioning / K. Okimura ; H. Kono ; O. Kohanawa ; T. Ishide ; Y. Nagura ; S. Tsubota
4.

図書
図書
4. Safety, reliability, and plant evaluations, student program : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000 (v. 5)
conference organized and sponsored by The American Society of Mechanical Engineers, ASME, Societeé Française d'Energie Nucléaire, SFEN, Japan Society of mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, ... [et.al.]
出版情報: New York : American Society of Mechanical Engineers, c2000  xvii, 886p. ; 28 cm
シリーズ名: Proceedings of the 8th International Conference on Nuclear Engineering 2000 : ICONE-8, Baltimore, Maryland, April 2-6, 2000 / conference organiaed and sponsored by American Society of Mechanical Engineers, ASME, Societé Française d'Energie Nucléaire, SFEN, Japan Society of Mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, Electric Power Research Institute, EPRI, International Atomic Energy Agency, IAEA ; v. 5
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5.

図書
図書
5. Nuclear fuel cycle, spent fuel, and radwaste management, codes, standards, and regulatory issues : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000 (v. 4)
conference organized and sponsored by The American Society of Mechanical Engineers, ASME, Societeé Française d'Energie Nucléaire, SFEN, Japan Society of mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, ... [et.al.]
出版情報: New York : American Society of Mechanical Engineers, c2000  xvi, 810p. ; 28 cm
シリーズ名: Proceedings of the 8th International Conference on Nuclear Engineering 2000 : ICONE-8, Baltimore, Maryland, April 2-6, 2000 / conference organiaed and sponsored by American Society of Mechanical Engineers, ASME, Societé Française d'Energie Nucléaire, SFEN, Japan Society of Mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, Electric Power Research Institute, EPRI, International Atomic Energy Agency, IAEA ; v. 4
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Nuclear Fuel Cycle, Spent Fuel, and Radwaste Management
Fuel Technology
ICONE 8-8143 The CAPRA-CADRA Programme / A. Vasile ; G. Vambenepe ; J. C. Lefevre ; K. Hesketh ; W. Maschek ; C. De Raedt ; D. Haas
ICONE 8-8207 Current Status of Studies on Oxide Pellet Fuel of Fast Reactors in Russia: Irradiation Experience and Post-Irradiation Examination Results / L. M. Zaboudko ; V. M. Poplavsky
ICONE 8-8221 Mixed Uranium-Refractory Carbide Fuels for Ultra-High Yield Reactors / T. W. Knight ; S. Anghaie
ICONE 8-8237 Irradiation Performance of a Prototypic Metallic Fuel for Fast Reactors / T. Ogata ; T. Yokoo
ICONE 8-8266 O/U ratio of UO[subscript 2] Pellets Sintered at Low Temperature and Reduced in Different Atmospheres / B. Ayaz ; A. N. Bilge
ICONE 8-8378 A Study of the Role of Higher Actinide Burning Fast Reactors in a Hypothetical Future UK Nuclear Fuel Cycle / D. Millington
ICONE 8-8394 Assembly and Fuel Pin Irradiation Behavior in the BN-350 Fast Reactor / V. N. Karaulov ; A. P. Blynski ; I. L. Yakovlev ; S. V. Golovin ; J. D. B. Lambert
ICONE 8-8528 Modal Parameters' Evaluation of a Full Scale PWR Fuel Assembly Submitted to Non-Evaluated Excitation / G. Gobillot ; J. Vallory ; R. Nhili
ICONE 8-8578 Advanced Research Reactor Fuel Development / M. K. Meyer ; G. L. Hoffman ; S. L. Hayes ; J. L. Snelgrove ; T. C. Wiencek ; C. R. Clark ; J. R. Stuart ; R. V. Strain
ICONE 8-8629 Russian Experience in Using UPuO[subscript 2] Vibropac Fuel Pins in Fast Reactors / A. A. Mayorshin ; O. V. Skiba ; V. A. Tsykanov ; V. A. Kisly
ICONE 8-8721 Preliminary Analysis on In-Reactor Performance of the Blanket Rod for HYPER / W. Hwang ; B. O. Lee ; W. S. Park
LWR Fuel Utilization
ICONE 8-8087 Plutonium Multi-Recycling in PWRs: The CORAIL Concept / S. Aniel ; M. Rohart ; A. Puill ; J. Bergeron ; G. Rouviere
ICONE 8-8103 High Energy Cores Experience at Westinghouse / A. L. Casadei ; M. Y. Young
ICONE 8-8232 Regulatory Perspectives on High Burnup Fuel Issues and Burnup Extension / M. S. Chatterton
ICONE 8-8294 System Modifications in Light Water Reactors for MOX Reloads
ICONE 8-8391 Nuclear Fuel Non-Destructive Testing Application for Dukovany NPP / M. Lahodova ; J. Vaverka ; M. Valach
Spent Nuclear Fuel and Nuclear Materials Management
ICONE 8-8005 In-Vessel Spent Fuel Storage and Simplified Handling System for a Nuclear Heating Reactor / H. Chang ; Y. Wu
ICONE 8-8164 Empirically-Based Approach for Prediction of Material Storage Temperatures in the Los Alamos Nuclear Materials Storage Facility / J. D. Bernardin ; S. Hopkins ; W. S. Gregory ; S. Zygmunt
ICONE 8-8180 Cooperative Research Program on Dry Cask Storage Characterization / R. M. Kenneally ; J. H. Kessler
ICONE 8-8187 Long-Term Storage or Burial of Discharged From Ships Defective, Non-Suited for Reprocessing and Spent Fuel and High-Activity Waste / S. D. Gavrilov ; N. N. Birillo ; S. A. Golovinsky ; V. A. Kremnev ; V V. Ruksha ; P. L. Smirnov ; A. A. Smolyakov
ICONE 8-8231 Investigation of PFBR Spent Fuel Clad Temperature During Handling / R. Gajapathy ; P. Selvaraj ; P. Chellapandi ; B. S. Sodhi ; S. C. Chetal ; S. B. Bhoje
ICONE 8-8342 Integrated Testing of a Drying Station for Spent Nuclear Fuel for the BN-350 Fast Reactor / C. E. Baily ; K. E. Rosenberg ; K. J. Allen ; E. A. Howden
ICONE 8-8348 Decrease of the LWR Spent Nuclear Waste Inventories and Cumulative Fissile Fuel Enrichment in Hybrid Reactor System / O. Ipek
ICONE 8-8396 The Management by EDF of Radioactive Waste Such as Spent Fuel Storage Rack, Steam Generators and Vessel Heads of PWR NPP / S. Rostain
ICONE 8-8398 The Design and Fabrication of the Transfer Canister for Spent Nuclear Fuel at the BN-350 Fast Reactor / D. K. Baird ; F. A. Orren
ICONE 8-8399 The Design and Installation of a Spent Fuel Packaging Cask for the BN-350 Reactor / L. J. Christensen ; M. J. Shannon
ICONE 8-8498 Design of Plant Hatch Independent Spent Fuel Storage Installation Pads / P. Hsu ; G. V. Jones ; D. P. Moore ; T. S. Springfield ; D. S. Walden
ICONE 8-8594 High Efficiency One-Stage Melting Converter Method for Vitrification of High-Level Radioactive Wastes / L. S. Pioro ; B. F. Sadovskiy ; I. L. Pioro
ICONE 8-8597 Design of a Cask Storage Building Based on Numerical Analysis of Natural Convection / H. Ijichi ; H. Kuwabara ; H. Takeda ; M. Mitsuda
ICONE 8-8627 Hybrid Recycle System for the Recovery of Dirty Plutonium and Pure Uranium / T. Fukasawa ; T. Sawa ; J. Yamashita ; M. Kamoshida ; A. Sasahira ; F. Kawamura
ICONE 8-8685 Spent Aluminum Plated Fuel Storage System at the Idaho National Engineering and Environmental Laboratory: Technologies and Experience / D. H. Miyasaki ; S. H. Rickard ; J. F. Hanek
Spent Nuclear Fuel and Waste Processing
ICONE 8-8099 Studsvik Processing Facility Pyrolysis/Steam Reforming Technology for Volume and Weight Reduction and Stabilization of LLRW and Mixed Wastes / J. B. Mason ; T. W. Oliver ; M. P. Carson ; G. M. Hill
ICONE 8-8115 Experience in Treatment and Conditioning of Gas Cooled Reactor Metallic Degraded Spent Fuels: The STAR Project / F. Boussard ; S. Fonquernie ; D. Dall'ava
ICONE 8-8195 Anodic Behaviors of Uranium and Zirconium During Electrorefining Spent Fuel in Molten Salt / S. X. Li
ICONE 8-8355 Structural Improvement on the Continuous Rotary Dissolver / T. Washiya ; T. Koizumi ; A. Aoshima
ICONE 8-8373 Development of New Treatment Method to Reduce the Volume of Low Level Liquid Wastes / Y. Saito ; N. Imamoto ; K. Miyata ; M. Karino
ICONE 8-8374 Development of New Treatment Method to Reduce the Volume of Chlorinated Organic Solid Wastes
ICONE 8-8388 Development of Integrated Treatment System for Liquid/Solid Wastes / H. Sagawa ; H. Fukui ; Y. Kuwayama ; T. Ueno ; K. Tanimoto ; H. Katayama ; N. Uda
ICONE 8-8449 Development of an Information Management and Communication System for the Second Progress Report for HLW Disposal in Japan / M. Shiotsuki ; H. Ishikawa ; S. Masuda ; S. Fusaeda ; I. Yanagisawa ; A. Neyama
ICONE 8-8540 Flowfield Characteristics in a Model Vaneless Diffuser Prior to Stall Inception / K. B. Abidogun ; S. A. Ahmed
ICONE 8-8541 Engineering and Acquisition of Equipment for Electrometallurgical Treatment of Spent Nuclear Fuel / J. E. Herceg ; K. J. Belcher ; L. Bova ; H. J. Haupt ; S. A. Kamal ; J. G. Saiveau
ICONE 8-8659 Anatomy of Waste Operations at Argonne National Laboratory - East / C. W. Grandy ; C. M. Rock
ICONE 8-8671 Technology Development for Nuclear Fuel Cycle: Radioactive Waste Treatment and Spent Fuel Storage / M. Kikuchi ; T. Yoshida ; M. Matsuda ; T. Izumida
ICONE 8-8702 Design and Development of a Cathode Processor for Electrometallurgical Treatment of Spent Nuclear Fuel / A. R. Brunsvold ; P. D. Roach ; B. R. Westphal
ICONE 8-8714 Mortar Matrices for Radioactive Waste Materials Physico-Chemical Characterization in Preaging Tests Due to Addition of the Polyethylene Granules and Powder / A. D. Peri
Codes, Standards, and Regulatory Issues
Design Codes and Standards Issues
ICONE 8-8227 Basis and Formulation of Toughness Requirements for Section III, Div. 3 of the ASME Code / S. Yukawa
ICONE 8-8238 Codes and Standards Redesign Using Advanced Web-Based Solutions / R. S. Hill III ; R. W. Barnes
ICONE 8-8411 Impact of Environmental Factors on Nuclear Components: A New Section III Appendix / W. Z. Novak
ICONE 8-8413 Recent Developments in the ASME Boiler and Pressure Vessel Code Section III / C. J. Pieper ; R. M. Jessee ; E. B. Branch
Risk-Informed ISI
ICONE 8-8165 A Risk-Informed Approach to IGSCC Weld Examinations / M. R. Graybeal
ICONE 8-8211 Industry and Regulatory Initiatives on Risk-Informed Inservice Inspection of Nuclear Piping / S. A. Ali ; S. Dinsmore
ICONE 8-8296 Developments on Implementation of U.S. NRC-Approved WOG Risk-Informed Inservice Inspection Methodology / K. R. Balkey ; N. B. Closky ; B. A. Bishop ; M. H. Canton ; R. L. Haessler ; G. L. Sharp ; P. R. Stevenson
ICONE 8-8298 Risk-Informed Inservice Inspection: Full Implementation Via Integration of Augmented Programs / P. O'Regan
ICONE 8-8383 Quantitative Assessment of a Risk Informed Inspection Strategy for BWR Weld Overlays / K. N. Fleming ; J. Mitman
ICONE 8-8622 Implementation Results of Risk-Informed Inservice Inspection Application at Arkansas Nuclear One, Unit Two / L. Shay ; M. J. Paterak ; K. C. Panther ; R. A. Fougerousse ; R. S. Smith
Risk-Informed IST
ICONE 8-8212 Cost/Benefit Evaluation of Implementing Pump and Valve RI-IST at a Nuclear Power Plant / C. W. Rowley
ICONE 8-8278 BandWOG Risk-Informed Inservice Testing Demonstration Project for Air-Operated Valves / G. K. Estep ; R. S. Enzinna
ICONE 8-8293 Implementation of an Air Operated Valve Program at Northern States Power Company / J. R. Schaefer ; R. B. Worrell ; P. Szetu
ICONE 8-8340 ASCO NPP Risk-Informed Inservice Testing Program for Check Valves / I. Mach ; R. Losa ; L. Mendez ; J. Faig
ICONE 8-8748 Operation and Maintenance Guideline on IST of Dynamic Restraints (Snubbers) for Nuclear Power Stations in Japan / H. Iwami ; M. Yokoe ; C. Kojima
Development of PRA Standard
ICONE 8-8255 Probabilistic Risk Assessment: Why a Standard Is Needed / M. T. Drouin ; M. A. Cunningham ; T. L. King ; G. M. Holahan ; R. J. Barrett ; A. M. Ramey-Smith
ICONE 8-8710 The American Nuclear Society PRA-Standards Project / R. J. Budnitz
MOV and AOV Issues
ICONE 8-8047 Verifying Design Basis Capability of Motor-Operated Valves / S. Loehein
ICONE 8-8228 NRC Regulatory and Research Activities on Performance and Safety-Related Motor-Operated Valves at U.S. Nuclear Power Plants / J. E. Jackson ; T. G. Scarbrough
ICONE 8-8326 Motor-Operated Valve (MOV) Activities in Korea and Canada / M. R. Holbrook ; W. T. Kim ; A. L. Grant
ICONE 8-8380 Summary of a Study of Air-Operated Valves in U. S. Nuclear Power Plants, NUREG/CR-6654 (INEEL/EXT-98-00383) / O. O. Rothberg
ICONE 8-8515 Motor-Operated Valve Performance Monitoring / P. W. Searfoorce ; G. F. Sessler
ICONE 8-8604 Joint Owner's Group Air Operated Valve Program / M. D. Coleman
Air and Gas Treatment Issues
ICONE 8-8153 High Efficiency Metal Filters for Nuclear Air and Gas Treatment: HEMA Filters and Their New AG-1 Code Section / L. D. Weber
ICONE 8-8630 Evaluation of HEPA Filter Service Life (RFP-5141) / J. K. Fretthold ; A. R. Stithem
ICONE 8-8631 ASME AG-1 Code on Nuclear Air and Gas Treatment / R. D. Porco
Cranes With Enhanced Safety for Increased Profit
ICONE 8-8077 X-SAM: The Single-Failure-Proof Crane System / J. E. Nelson
ICONE 8-8544 ASME Nuclear Crane Standards for Enhanced Crane Safety and Increased Profit / S. N. Parkhurst
ICONE 8-8545 Flux Vector Controls for Increased Reliability, Performance, and Safety / A. J. Orgovan
ICONE 8-8546 Nuclear Containment Telescoping Boom Jib Crane / D. P. Weber
ICONE 8-8547 Cranes at NASA's Kennedy Space Center Utilizing Enhanced Mechanical and Electrical Safety Features / B. P. Lytle
Nuclear Quality Assurance Issues
ICONE 8-8215 Nuclear Quality Assurance Standards and Regulations: Evolution and Issues / M. E. Langston ; S. A. Bernsen
ICONE 8-8248 Software Quality Assurance and the NQA-1 Standard / R. C. Schrotke
ICONE 8-8694 Graded Application of NQA Standards to Research and Development Activities / F. C. Hood
Other Regulatory Issues
ICONE 8-8365 Maintaining Nuclear Safety Competence of Regulatory Staff Into the 2000's / A. M. Omar ; I. Grant ; N. Belisle
C and S Strategic Planning Issues
ICONE 8-8782 Strategic Planning for Codes and Standards in Japan / M. Higuchi
ICONE 8-8783 Strategic Planning for ASME Nuclear Codes and Standards / J. H. Ferguson
ICONE 8-8636 Recent Changes in French Regulation and Codes for Nuclear and Non-Nuclear Pressure Components / C. Faidy
ASME Research Issues
ICONE 8-8299 The Development of Risk-Informed Qualification (RIQ) Guidelines for Active Mechanical Equipment / B. M. Ayyub ; R. K. Perdue
ICONE 8-8321 Improved Methods for Estimating the Distribution and Density of Defects in Welds Used in Reactor Piping / O. J. V. Chapman ; F. A. Simonen ; R. S. DeCesare
ICONE 8-8354 Risk-Informed Technology Developments Within the American Society of Mechanical Engineers for Nuclear Power Plants
ASME Code Case N-589 Cured-In-Place-Pipe
ICONE 8-8243 Use of Reinforced Epoxy as a Structural Lining System / R. H. Walker
ICONE 8-8389 Why Was the N-589 Code Case Developed......and Revised? / J. T. Conner ; C. W. Wesley
ICONE 8-8681 Cured-in-Place Piping Application for Structural and Pressure Boundary Integrity / J. A. Charest
Author Index
Nuclear Fuel Cycle, Spent Fuel, and Radwaste Management
Fuel Technology
ICONE 8-8143 The CAPRA-CADRA Programme / A. Vasile ; G. Vambenepe ; J. C. Lefevre ; K. Hesketh ; W. Maschek ; C. De Raedt ; D. Haas
6.

図書
図書
6. Thermal hydraulics : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000 (pt. A ; pt. B)
conference organized and sponsored by The American Society of Mechanical Engineers, ASME, Societeé Française d'Energie Nucléaire, SFEN, Japan Society of mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, ... [et.al.]
出版情報: New York : American Society of Mechanical Engineers, c2000  2 v. (xx, 1546p.) ; 28 cm
シリーズ名: Proceedings of the 8th International Conference on Nuclear Engineering 2000 : ICONE-8, Baltimore, Maryland, April 2-6, 2000 / conference organiaed and sponsored by American Society of Mechanical Engineers, ASME, Societé Française d'Energie Nucléaire, SFEN, Japan Society of Mechanical Engineers, JSME ; co-sponsored by Department of Energy - Office of Nuclear Energy, Science and Technology, Electric Power Research Institute, EPRI, International Atomic Energy Agency, IAEA ; v. 6
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Thermal Hydraulics / Part A：
Two-Phase Flow and Heat Transfer Fundamentals
ICONE 8-8024 Three-Dimensional Standing Pressure Waves in Bubbly Mixtures / H. Tinoco ; S. Ahlinder
ICONE 8-8037 Interfacial Area Transport in Bubbly Flow Systems / T. Hibiki ; M. Ishii
ICONE 8-8045 An Extended Two-Fluid Model for Interface Behavior in Gas-Liquid Two-Phase Flow / A. Minato ; K. Takamori ; N. Ishida
ICONE 8-8107 Analysis of Vaporization and Condensation in the Sebulon Experiment / S. Pigny ; P. Coste
ICONE 8-8108 Analysis of Two Phase Flow Phenomena in the Burty and Castillejos Experiments
ICONE 8-8147 A Description of the Richert-Franz Film Boiling Convective Heat Transfer Coefficient Correlation / S. C. Franz ; K. D. Richert
ICONE 8-8169 Velocity of a Single GSA Plug Rising Through a Particle-Gas-Liquid Three-Phase Flow (Analysis of Particle Introduction Effects) / Y. Koizumi ; J. Shimada ; H. Ohtake
ICONE 8-8183 Two-Phase Flow Instabilities in a Natural Circulation Rectangular Loop / A. Belchior, Jr. ; J.-L. F. Bastos ; G. Sabundjian ; D. A. Andrade
ICONE 8-8393 Development and Validation of Drift Flux Model for Different Geometries / A. Srivastava ; H. G. Lele ; S. K. Gupta ; H. S. Kushwaha ; V. Venkat Raj
CHF and Post-CHF Thermal Hydraulics
ICONE 8-8079 Semi-Scale Test on Post DNB Heat Transfer of PWR Fuel Assembly / K. Murai ; N. Kono ; K. Mishima ; K. Hori ; T. Suemura ; Y. Akiyama
ICONE 8-8092 Some Problems of Lookup Tables Method Usage for CHF Determination / M. A. Gotovsky ; M. A. Kvetniy
ICONE 8-8126 Critical Heart Fluxes on Short Vertical Tube Inner Surface in Water Flowing Upward: Effect of Tube Inner Diameter and Application to Thermal Analysis of Divertor Plate / G. Sato ; K. Hata ; M. Shiotsu ; N. Noda
ICONE 8-8313 Extremely High CHF Prediction for Subcooled Flow Boiling / W. Liu ; H. Nariai ; F. Inasaka
ICONE 8-8350 Effect of Flow Obstruction Shape on the Critical Heat Flux / I. L. Pioro ; D. C. Groeneveld ; S. C. Cheng ; S. Doerffer ; A. Z. Vasic
ICONE 8-8432 Validation of the THYC Software for CHF Analysis of PWR Core / J. Mur ; J. Lajeunesse
ICONE 8-8523 Application of ANN in Tube CHF Prediction With BP and SA Algorithm / S. Jianqiang ; H. Yanping ; C. Bingde ; Z. Jizhou
ICONE 8-8590 On Dryout Heat Flux of a Particle Debris Bed With a Downcomer / M. J. Konovalikhin ; Z. L. Yang ; M. Amjad ; B. R. Sehgal
New Developments in Thermal Hydraulic Modeling
ICONE 8-8017 Simulation Problems of Emergency Natural Convection Heat Removal in the Upper Plenum of LMF Using Water / P. A. Ushakov ; A. P. Sorokin ; N. M. Matjukhin
ICONE 8-8034 Analysis and Modeling of the Heat Transfer in Square and Hexagonal Rod Bundles Encased by a Shroud for Laminar Longitudinal Gas Flow; Extension of the ATHLET-CD Heat Transfer Models / T. Steinroetter ; H. Unger
ICONE 8-8036 A New Neural Network Concept for Control of Nuclear Reactor Systems / B. D. Baptista Filho ; E. L. Lustosa Cabral
ICONE 8-8043 Performance Analysis of Multilayer Steel-Foil Insulation / L. A. Adamovich
ICONE 8-8101 FRED: Calculational Model of Fuel Rod Behavior Under Accident Conditions Coupled With RELAP5/MOD3 / K. Mikityuk ; P. Fomichenko
ICONE 8-8106 Analysis of the MHYRESA-Hot Leg Entrainment Tests / G. Geffraye ; B. Faydide ; S. Laroche ; G. Ratel
ICONE 8-8119 Application of the Drift Flux Model to Gas-Liquid Two-Phase Flows With Obstacles / N. Fujimoto ; N. Kamesako ; T. Dohnen ; K. Morita ; K. Fukuda
ICONE 8-8124 Improvement of the CCFL Models of RELAP5/MOD3.2.2b Code in a Horizontal Pipe / S. Heo ; H. C. No ; C. K. Sung ; S. H. Ghyym
ICONE 8-8188 Development and Validation of the Fast Running Thermohydraulic Model SMABRE for Simulator Purposes / J. Miettinen ; A. Hamalainen
ICONE 8-8331 A Calculation Procedure for Mass and Momentum Transfer in the Flow Developing Region of Three Dimensional Rectangular Channels / S. Richter ; M. Aritomi
ICONE 8-8360 Development of a Particle Calculation Model for Fluid-Structural Interaction / Y. Chikazawa ; S. Koshizuka ; Y. Oka
ICONE 8-8431 Evaluation of Prediction Models for Subcooled Water Flow Boiling CHF for High-Heat-Flux Applications / Y.-M. Kwon ; S.-H. Chang
ICONE 8-8445 Calculation of Standalone Passive Safety Injection System With New Thermal Stratification Solution Method of APROS Code / J. Vihavainen
ICONE 8-8496 Internal Heat Transfer to Viscoelastic Flows Through Porous Media / B. K. Rao ; J. McDevitt ; D. Vetter
ICONE 8-8549 Simulation of Hydrogen Behavior in Large Cells / J.-P. Simoneau
ICONE 8-8653 Thermal Hydraulic Test and Verification of Thermal Hydraulic Computer Code for Two-Phase Flow in U-Bend Tube / M. Takai ; T. Iwase ; S. Uwagawa ; Y. Hirao ; T. Suzuta ; T. Ueno ; J. Kasahara ; J. Kodama ; K. Tomomatsu
Thermal Hydraulics Fundamentals
ICONE 8-8027 Local Heat and Mass Transfer Coefficient in Condensation of Steam With Non-Condensable Gas in a Tube Bank / G. Avakian
ICONE 8-8053 Flooding in Vertical Rod Bundles / S. V. Svetlov ; S. B. Alexeev ; Y. N. Ilyukhin ; V. O. Kuhtevich ; V. G. Sidorov
ICONE 8-8093 The Theoretical Model of Thermal Interaction Between Uranium Bioxyde and Sodium / P. Syrmalenios
ICONE 8-8308 Theoretical Solutions and a Correlation for Forced Convection Film Boiling Heat Transfer From Horizontal Cylinders in Saturated Liquids / Q. Liu ; A. Sakurai
Benchmark Analysis and Assessment of Thermal Hydraulic Codes
ICONE 8-8039 DNP/3D PWR Main Steam Line Break Benchmark Analyses / R. C. Kern
ICONE 8-8086 Natural Circulation Behavior Analysis of the Penn State Low Pressure Integral Test Facility / G. Wang ; L. E. Hochreiter
ICONE 8-8124 Improvement of the CCFL Models of the RELAP5/MOD3.2.2b Code in a Horizontal Pipe
ICONE 8-8181 The Best Estimate Large Break Loss of Coolant Accident Analysis Using TRAC-M/F77 for Korean Next Generation Reactor / H.-G. Kim ; B. S. Kim ; S. J. Cho
ICONE 8-8219 RELAP5 Modeling of Subcooled Boiling in Vertical Flow / B. Koncar ; B. Mavko
ICONE 8-8533 Two-Phase Flow Instability in Steam Venting Line / Y. Kukita ; Y. Tsuji ; T. Yonomoto
ICONE 8-8588 Summary of the Second Exercise of the OECD/NRC PWR MSLB Benchmark / J. B. Taylor ; K. N. Ivanov ; A. J. Baratta
BWR Transient Analysis and Stability
ICONE 8-8102 Influence of Nozzle Diameter on Reactor Internal Pump Performance in Reactor Pressure Vessel / S. Takahashi ; K. Shiina ; H. Takehara ; M. Tanaka ; K. Umemori ; K. Moriya ; H. Soneda
ICONE 8-8189 RECRIT Code for BWR Recriticality Analysis / W. Frid ; F. Hoejerup ; I. Lindholm
ICONE 8-8450 Development of Improved Orifice in BWR Fuel Support / M. Akiba ; S. Morooka ; K. Shirakawa ; K. Chuman
ICONE 8-8568 Two-Phase Flow Stability in Low Pressure Parallel Vertical Heated Annuli / N. K. Popov ; U. S. Rohatgi ; H. E. C. Rummens ; R. B. Duffey
Advances in Thermal Hydraulic Measurement Methods
ICONE 8-8182 Quantitative Assessment of BETHSY 6.2 TC Test Simulation / S. Hrvatin ; A. Prosek ; I. Kljenak
ICONE 8-8285 Effect of Pipe Diameter on Flow Pattern Transitions and Void Fraction of Air-Water Flow in Vertical Pipes / M. Shoukri ; B. Stankovic ; I. Hassan ; J. Dimmick
ICONE 8-8327 Interfacial Area Measurement in a Bubbly-Slug Transition Air-Water Flow / X. Fu ; Y. Mi
ICONE 8-8330 Flow Structure of Developing Steam-Water Two-Phase Flow in a Large-Diameter Pipe / K. Yoneda ; A. Yasuo ; T. Okawa ; S.-R. Zhou
ICONE 8-8333 Investigation on the Bubble Boundary Layer in Bubbly Counter-Current Flows / Y. Suzuki ; M. Nakagawa ; H. Kikura ; M. Mori
ICONE 8-8367 Analysis on the Self-Induced Sloshing Using Particle Image Velocimetry / K. Okamoto ; S. Saeki ; H. Madarame ; H. Hu ; T. Saga ; T. Kobayashi
ICONE 8-8405 Noise Reduction Techniques for the Particle Image Velocimetry: Application to an Experimental Study on Natural Convection in a Fast Reactor Core / N. Kimura ; Y. Miyake ; A. Yasuda ; H. Miyakoshi ; M. Nishimura ; A. Tokuhiro ; H. Kamide
ICONE 8-8426 Visualization and Measurement of Subcooled Water Jet Injection Into Molten Alloy / Y. Sibamoto ; H. Nakamura ; H. S. Park ; Y. Anoda
ICONE 8-8476 Local Measurement of Liquid Velocity in Bubbly Flow / X. Sun ; T. Smith ; S. Kim
ICONE 8-8481 Liquid Velocity Measurement in Vertical Slug Flow
ICONE 8-8586 Internal Waves Excited by Vertical Vibration of Stratified Fluids Confined in a Circular Cylinder / T. Ito ; H. Asahina ; J. Shimizu
ICONE 8-8623 Simultaneous Measurement System on Free Surface and Liquid Velocity Distribution Using Particle Image Velocimeter and Laser Focus Displacement Meter / K. Kobayashi ; T. Takamasa ; K. Okomoto
ICONE 8-8686 Experimental Study on Condensation Phenomena in Spray Cooling / M. Takahashi ; S. Kitagawa ; H. Murakoso ; A. K. Nayak
Safety Related Thermal Hydraulic Experiments and Modeling
ICONE 8-8134 Impact of Secondary Injection Conditions on PWR Thermal Hydraulics: Experimental Investigations in the PKL-Test Facility / T. Mull ; P. Burwitz ; K. Umminger
ICONE 8-8135 Effect of Axial Heat Flux Distributions on Critical Heat Flux Under Low Flow and a Wide Range of System Pressures With Vertical Annulus / S. K. Moon ; S. Y. Chun ; H. J. Chung ; S. K. Yang ; M. K. Chung
ICONE 8-8166 Experimental Investigation of Subcooled Boiling / M. Bartel ; R. Situ ; T. Masukawa
ICONE 8-8191 The In-Pile Research of Design-Basis and Severe Accidents in Pressurized Water Reactors / Y. N. Kuznetsov ; V. P. Smirnov ; I. T. Tretyakov ; M. N. Svyatkin ; V. M. Machin ; V. M. Spasskov ; G. M. Antonovsky
ICONE 8-8292 An Extension of the Slug Flow Transition Model to Include the Steam Condensation Effect on CCFL / M.-H. Chun ; S.-O. Yu ; H.-Y. Nam
ICONE 8-8539 Effect of Heat Input on Minimum Heat Flux Temperature Observed at Reflood Experiment With 4[times]4 Bundle Test Section Under High-Pressure / T. Iguchi ; S. Ohmizu
ICONE 8-8565 Experimental Investigation of Condensation and Mixing During Venting of a Steam/Non-Condensable Gas Mixture Into a Pressure Suppression Pool / C. De Walsche ; F. de Cachard
ICONE 8-8713 Semi-Scale Rod Bowing DNB Test of PWR Fuel Assembly / K. Miyazaki
Subchannel Analysis of Thermal Hydraulics
ICONE 8-8185 Thermal-Hydraulic Analysis of Small Break LOCA for Indian PHWRs With RELAP-COBRA / D. Mukhopadhyay ; G. H. Behera ; S. K. Bandyopadhyay
ICONE 8-8186 Transient Hydraulic Forces Experienced by the Nuclear Fuel Bundles Arising From a Double-Ended Guillotine Rupture of a Reactor Inlet Feeder
ICONE 8-8625 Thermalhydraulic Behaviour in a Rectangular Loop / M. Misale ; M. Frogheri ; F. D'Auria
Computational Thermal Hydraulic Tools for Simulation and Analysis of LWR Accidents
ICONE 8-8073 Numerical Examination of Coolant Flow Mixing in Nuclear Fuel Assembly With Mixing Promoters / W. K. In ; D. S. Oh ; T. H. Chun ; Y. H. Jung
ICONE 8-8128 Optimisation of Dousing Flow for Dousing System on RAPS / P. K. Sharma ; S. K. Haware ; A. K. Ghosh
ICONE 8-8277 Development of Thermal-Hydraulic Computer Code (Two-Fluid Model) for Steam Generator / Y. Kondo ; K. Kawanishi ; A. Tsuge
ICONE 8-8534 Assessment of the Multi-Dimensional Capabilities of an Advanced Containment Code: A Basic Approach / M. Andreani ; B. L. Smith
Two-Phase Computational Fluid Dynamics and Heat Transfer / Part B：
ICONE 8-8012 A Characteristic Analysis for the One-Dimensional Two-Fluid Model / J. H. Song ; S. W. Hong
ICONE 8-8055 Computation of Two-Phase Flow in Steam Generator Using Domain Decomposition and Local Zoom Methods / M. Belliard ; M. Grandotto
ICONE8-8058 Characteristics and Stability of a Two-Fluid Model for Bubbly Two-Phase Flow / I. Kataoka
ICONE8-8121 CFD Simulation on Aerosol Impaction and Deposition Analysis in a Passive Containment Condenser / W. H. W. Ludwig ; K. E. J. Lehtinen ; J. Pyykonnen ; D. P. Brown ; J. Enriquez Paraled ; J. K. Jokiniemi
ICONE8-8170 A Two-Phase CFD Model for Direct Calculation of Heat Transport With Phase Change / G. Chen ; S. Anghaie ; C. Boyd
ICONE8-8719 Development of a Multi-Dimensional Upwind Solver for Two-Phase Water/Steam Flows / I. Toumi ; A. Kumbaro ; V. Seignole ; H. Paillere
Thermal Hydraulic Simulation of PWR Transients
ICONE8-8149 A RELAP5 Reactor Vessel Nodalization Sensitivity Study on Multidimensional Effects in Realistic Large Break LOCA / R. P. Martin
ICONE8-8241 Assessment of French Reactor Pressure Vessel Integrity: A Thermal Hydraulics and Fracture Mechanics Analysis of the Small Break Loss of Coolant Accidents (SBLOCA) / F. Ternon-Morin ; P. Haussaire ; S. Bellet ; A. Martin ; G. Bezdikian
ICONE8-8242 Development of Thermal-Mixing Analysis Model for Safety Injection at Partial Loop Stagnation of NPP / K. M. Hwang ; H. K. Youm ; T. E. Jin
ICONE8-8410 A Study on the Thermal Hydraulic Characteristics of Flow in the Primary System of SMART Depending on the Operation Modes / H.-S. Kang ; J.-P. Kim ; D. Y. Chi ; H. Y. Kim ; D.-J. Lee
ICONE8-8559 Critical Pressure Ratio and Critical Flow Rate in a Safety Valve / S. W. Kim ; S. K. Lee
LWR Ex-Vessel Thermal Hydraulics
ICONE8-8214 Numerical Modelling of Melt Spreading Phenomena / N. Reinke ; M. K. Koch ; W. Schuttz ; G. Fieg
ICONE8-8363 A Preliminary Study on the Corium Melting and Release for FCI Experiment / J. H. Kim ; S. Y. Park ; B. T. Min ; H. D. Kim
ICONE8-8403 The Effect of Containment Nodalization on Hydrogen Concentration During a Severe Accident / S.-D. Lee ; K. Y. Suh ; G. C. Park
ICONE8-8440 Measurement of Dynamic Interface Distribution in Immiscible Two-Component Fluids Using a Fast X-Ray CT Scanner / M. Misawa ; N. Takada ; N. Ichikawa ; M. Akai ; Y. Kato
ICONE8-8478 Interfacial Transport Phenomena and Stability in Molten Metal-Water Systems / H. Kim ; M. Anderson ; R. Bonazza ; M. Corradini ; D. H. Cho
ICONE8-8536 Study on Ex-Vessel Cooling of RPV (Critical Heat Flux and Enhancement of CHF Induced by Ultrasonic Wave on Inclined Surfaces) / K. Takano
ICONE8-8639 Experiments on In-Vessel Melt Pool Formation and Convection With NaNO[subscript 3]-KNO[subscript 3] Salt Mixture as Melt Simulant / G. Kolb ; S. A. Theerthan
ICONE8-8655 Research Work for the Development of Ex-Vessel Core Melt Mitigation / W. Steinwarz
ICONE8-8809 Computational Analysis of Transient 3D-Melt-Water Interactions / N. I. Kolev
Thermal Hydraulics of Advanced Nuclear Reactors
ICONE8-8148 A Study of Return to Saturation Oscillations in the OSU APEX Thermal Hydraulic Testing Facility
ICONE8-8163 Experimental Investigation of Circulation in Homogenous Reactor With Using Simulating Media / V. A. Reshetov ; V. A. Moskin ; E. K. Karasiov ; G. N. Kudinov ; V. A. Shishov ; V. S. Bashkin
ICONE8-8280 Post Test Analyses of Four PANDA System Tests Using RELAP5/Mod3.2 / D. Lubbesmeyer
ICONE8-8402 Flow Pattern and Thickness of DVI Impingement for a Vertical Flat Plate / S. H. Yoon ; L. K. Park
ICONE8-8430 New Aspects of Emergency Decay Heat Removal From a Pb/Bi-Cooled ADS by Auxiliary Cooling / J. Karlsson ; H. Wider
ICONE8-8607 TEPSS: Technology Enhancement for Passive Safety Systems: Final Results / J. Hart ; W. J. M. Slegers ; S. L. de Boer ; M. Huggenberger ; J. Lopez Jimenez ; J. L. Munoz-Cobo Gonzalez ; F. Reventos Puigjaner
Innovation in Liquid Metal Cooled Reactors
ICONE8-8208 Thermal Hydraulic Analysis of Sodium Mixing in IHX Outlet Plenum / R. Gajapathy ; P. Selvaraj ; P. Chellapandi ; S. C. Chetal ; S. B. Bhoje
ICONE8-8210 Direct Numerical Simulation of a Combustion Experiment of a Free-Falling Liquid Sodium Droplet / Y. Okano ; A. Yamaguchi
ICONE8-8220 Overview of the Use of ATHENA for Thermal-Hydraulic Analysis of Systems With Lead-Bismuth Coolant / C. B. Davis ; A. S. Shieh
ICONE8-8370 Temperature Distribution in the Reactor Vessel of KALIMER / E.-K. Kim ; Y. S. Sim ; S.-O. Kim ; Y.-S. Kim ; M.-H. Wi
ICONE8-8409 A Summary of Ultrasonic Thermometer Sodium Test Results for Pipe-Flow / H. Hayashida ; A. T. Tokuhiro ; M. Ueda ; K. Ara
ICONE8-8418 Development of Subchannel Code for LMR Core Thermal Hydraulic Analysis / W.-S. Kim ; Y.-G. Kim
ICONE8-8522 Natural Circulation Heat Transfer Analysis for a Liquid Metal Reactor / J.-E. Chang
ICONE8-8739 Void Fraction Prediction for the PB-BI/Water Direct Contact Nuclear Reactor / J. Buongiorno ; N. E. Todreas ; M. S. Kazimi
ICONE8-8769 Study on Applicability of Direct Contact Heat Transfer Steam Generators for LMFBRs / I. Kinoshita ; Y. Nishi ; M. Furuya
Rapid Boron-Dilution Transients
ICONE8-8482 An Analysis of Internal Dilute Slug Injection in a PWR Integral Test Facility / B. Woods ; M. Gavrilas ; D. Shaool
ICONE8-8503 Lattice Boltzmann Simulation of a Rapid Boron-Dilution Transient in a PWR Integral Test Facility / C. M. Teixeira
ICONE8-8524 Benchmark Analysis of Rapid Boron Dilution Transient / T. Morii ; H. Terasaka ; E. Hirano
ICONE8-8621 Investigation of Coolant Mixing in Pressurized Water Reactors at the Rossendorf Mixing Test Facility Rocom / G. Grunwald ; T. Hohne ; H.-M. Prasser
ICONE8-8658 Overview of ISP No. 43 on Rapid Boron-Dilution Transient Simulations
Advances in Coupled Thermal Hydraulic and Neutronic Codes
ICONE8-8029 MANTA: A Modular Advanced Neutronic and Thermal Hydraulic Analysis Code / J.-L. Gandrille ; A. Haulbert ; J.-F. Petetrot
ICONE8-8696 Analysis of the OECD MSLB Benchmark With the Coupled Code DYN3D/ATHLET / S. Kliem ; U. Grundmann ; U. Rohde
ICONE8-8774 Innovative Features in the RELAP5/PANBOX/COBRA Neutron-Kinetics/Thermal-Hydraulics Code System / D. G. Cacuci
ICONE8-8818 Analysis of Different Mapping Schemes of Thermo-Hydraulic Channels for the OECD PWR Main Steam Line Break Benchmark Phase 3 / S. Langenbuch ; K.-D. Schmidt ; K. Velkov
Thermal Hydraulics of VVER and RBMK
ICONE8-8184 An Experimental Investigation of 4.0% Upper Plenum Break Accident on PSB-VVER Test Facility / I. A. Lipatov ; G. I. Dremin ; S. A. Galtchanskaia ; S. V. Zevalkin ; Y. S. Gorbunov ; I. V. Elkin
ICONE8-8253 LOCA Scaling Effect for ISB-VVER, PSB-VVER Test Facilities and VVER-1000 / E. Y. Chtchepetilnikov ; O. I. Melikhov ; V. I. Melikhov
ICONE8-8254 Post-Test Analysis of ISB-VVER Test Facility Up 11% Leak at ECCS Operation With Help of the Codes RELAP and ATHLET / S. S. Pylev
ICONE8-8303 RELAP5-3D Code Validation for RBMK Phenomena / J. E. Fisher
ICONE8-8570 RELAP5 Code Assessment Activities for Application to the RBMK and VVER Reactor Designs / J. Roglans ; P. Garner ; J. Ahrens ; V. Blinkov ; O. Melikhov ; P. Roth ; P. Bayless ; B. Schmitt ; G. Savvatimski
ICONE8-8680 Approach to the Thermal Hydraulic Codes Applied to VVER Calculation Verification / V. N. Kolochko ; M. M. Kovetskaya
Thermal Hydraulics of Severe Accidents
ICONE8-8146 A Computational Model for the Analysis of Heat Transfer Characteristics in Liquid Metal Pool Under a Solidification Process: MELTPOOL / K. I. Ahn ; S. B. Kim ; D. H. Kim
ICONE8-8190 A Process Model for Fast Prediction of Radioactive Relseases From a LWR / K. Herviou ; P. Schmuck
ICONE8-8206 Effects of Aspect Ratio Change and Coolant Boiling on Natural Convection With Crust Formation / R.-J. Park ; K.-H. Kang ; S.-B. Kim ; H.-D. Kim ; J.-S. Cho ; C.-H. Chung
ICONE8-8290 Reactor Cavity Melt Spread and Ablation Analysis Using the MELTSPREAD-1 Computer Code / Y. M. Song ; J. H. Park ; S. D. Kim
ICONE8-8566 TMI-2 Simulation by RELAP5/SCDAP and COMETA Codes / A. Annuziato ; A. Franceschini ; C. Addabbo
ICONE8-8589 Experimental Investigation on Re-Spreading Phenomena
Thermal Hydraulics of Small Flow Passages
ICONE8-8142 The Development of Micro-Nozzles via MEMS Technology and Effects on Spray Characteristics / S. Baik ; S. Kang ; J. P. Blanchard ; M. L. Corradini
ICONE8-8705 Experimental Investigation of Cross Flow Between Two Parallel Micro-Channels / J. A. Khan ; A. N. Pohan ; X. Ma ; C. A. Rhodes
ICONE8-8707 The Onset of Flow Instability in Uniformly Heated Horizontal Narrow Annuli / A. M. Blasick ; M. F. Dowling ; S. I. Abdel-Khalik ; S. M. Ghiaasiaan ; S. M. Jeter
ICONE8-8708 Mechanistic Nonequilibrium Modeling of Critical Flow of Subcooled Liquids Containing Dissolved Noncondensables Using the Dynamic Flow Regime Map / H. Geng
ICONE8-8709 Turbulent Wall Friction and Forced Convection Heat Transfer in a Trapezoidal Channel / T. J. Remley
Validation and Uncertainty of Systems Transients Codes
ICONE8-8069 Architecture of the USNRC Consolidated Code / J. Mahaffy ; J. Uhle ; J. Dearing ; T. Downar ; R. Johns ; C. Murray
ICONE8-8080 Preliminary Assessment of an In-Vessel Core Retention Strategy Using Best Estimate Tools / P. Meloni ; P. Richard ; B. Spindler
ICONE8-8281 Assessment of RETRAN-3D Against Experimental Loss of Coolant Scenarios / R. Macian ; P. Coddington
ICONE8-8283 Assessment of RETRAN-3D and VIPRE-02 Void Prediction Against Experimental Transient Data / Y. Aounallah ; P. Stangroom
ICONE8-8325 Initial and Boundary Conditions to LOCA Analysis: An Examination of the Requirements of Appendix K / D. E. Bessette
ICONE8-8479 Recirculating Flow Anomaly Problem Solution Methods / D. S. Lucas
ICONE8-8711 A Noding Sensitivity Analysis Using COBRA-TF and the Effect of Spacer Grids During Core Reflood / C. Frepoli ; F. B. Cheung
ICONE8-8737 Consideration of Bifurcations Within the Internal Assessment of Uncertainty / W. Giannotti ; A. Piagentini
Thermal Hydraulic Code Graphical Interface and Visualization
ICONE8-8390 Impact of Functional Objectives on the Design and Implementation of the SNAP Model Editor / B. J. Gitnick
ICONE8-8436 Mixed Language Programming in Engineering Application HYRECAT
ICONE8-8676 RELAP5/RGUI Architectural Framework / J. A. Galbraith ; G. L. Mesina
Thermal Hydraulics (Invited Papers)
ICONE8-8619 Research Needs Based on Reactor Operational Experiences / D. F. Ross, Jr.
ICONE8-8626 Evolution of CHF and Post-CHF Prediction Methods for Fuel Bundles / L. K. H. Leung
ICONE8-8729 The Rush to Heavy Liquid Metal Reactor Coolants: Gimmick or Reasoned / B. W. Spencer
ICONE8-8754 ANRC Sponsored University Nuclear Research / F. J. Davis
ICONE8-8826 Comparison of Sodium and Lead/Lead-Bismuth as a Coolant and LMFR Safety / H. Ninokata ; P. L. Kirillov
Author Index
Thermal Hydraulics / Part A：
Two-Phase Flow and Heat Transfer Fundamentals
ICONE 8-8024 Three-Dimensional Standing Pressure Waves in Bubbly Mixtures / H. Tinoco ; S. Ahlinder
7.

図書
図書
7. 1997 ASME/SFEN/JSME ICONE5 : the 5th International Conference on Nuclear Engineering : presented at the 5th International Conference on Nuclear Engineering, May 25-29, 1997, Nice, France
sponsored by The Nuclear Engineering Division, ASME, French Nuclear Energy Society, SFEN, Japan Society of Mechanical Engineers, JSME
出版情報: New York : American Society of Mechanical Engineers, c1997  lxxvi, 490 p. ; 22 cm
所蔵情報: loading…
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