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 |