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ASME/JSME Joint International Conference on Nuclear Engineering ; American Society of Mechanical Engineers ; 日本機械学会
出版情報: New York, N.Y. : ASME, c2004  xvi, 907 p. ; 28 cm
シリーズ名: Proceedings of the 12th International Conference on Nuclear Engineering (ICONE12)--2004 : presented at 12th International Conference on Nuclear Engineering, April 25-29, 2004, Arlington, Virginia, USA / sponsored by Nuclear Engineering Division, ASME, the Japan Society of Mechanical Engineers, JSME ; v. 1
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図書

図書
ASME/JSME Joint International Conference on Nuclear Engineering ; American Society of Mechanical Engineers ; 日本機械学会
出版情報: New York, N.Y. : ASME, c2004  xvi, 864 p. ; 28 cm
シリーズ名: Proceedings of the 12th International Conference on Nuclear Engineering (ICONE12)--2004 : presented at 12th International Conference on Nuclear Engineering, April 25-29, 2004, Arlington, Virginia, USA / sponsored by Nuclear Engineering Division, ASME, the Japan Society of Mechanical Engineers, JSME ; v. 2
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図書

図書
ASME/JSME Joint International Conference on Nuclear Engineering ; American Society of Mechanical Engineers ; 日本機械学会
出版情報: New York, N.Y. : ASME, c2004  xvi, 877 p. ; 28 cm
シリーズ名: Proceedings of the 12th International Conference on Nuclear Engineering (ICONE12)--2004 : presented at 12th International Conference on Nuclear Engineering, April 25-29, 2004, Arlington, Virginia, USA / sponsored by Nuclear Engineering Division, ASME, the Japan Society of Mechanical Engineers, JSME ; v. 3
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cosponsored by the British Society for Strain Measurement ... [et al.]
出版情報: Bethel, Conn. : Society for Experimental Mechanics, 2000  xxxiii, 1020, xl p. ; 28 cm
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sponsored by the American Society of Mechanical Engineers, ASME ; co-sponsored by the Japan Society of Mechanical Engineers, the Canadian Society for Mechanical Engineering, L'Association Française de Mécanique ; edited by Michael P. Païdoussis
出版情報: New York, N.Y. : American Society of Mechanical Engineers, c2002  2 v. (xv, 1401 p.) ; 28 cm
シリーズ名: AMD ; vol. 253
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cosponsored by IEEE Industrial Electronics Society ... [et al.] ; technically sponsored by Japan Society of Mechanical Engineers ... [et al.] ; in cooperation with Chubu Bureau of International Trade & Industry of MITI ... [et al.]
出版情報: [New York] : Institute of Electrical and Electronics Engineers , Piscataway, N.J. : IEEE Operations Center, c2000  vii, 247 p. ; 28 cm
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図書

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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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目次情報: 続きを見る
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
8.

図書

図書
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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9.

図書

図書
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
10.

図書

図書
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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