ICONE16-48047  

Transient Detection And Identification System Based on Artificial Neural Networks

ICONE16-48063  

Steam Generator in-service inspections at Paks NPP

ICONE16-48086  

Restart of Browns Ferry Nuclear Plant Unit 1

ICONE16-48099  

The Main Changes and Consequences by Burnup Extensions in PWRs: Some Recommendations for Negative Plant Performance Issues Limitations

ICONE16-48107  

Optimal Preventive Maintenance Policy Under a Budget Constraint

ICONE16-48108  

Optimizing Project Prioritization Under Budget Uncertainty

ICONE16-48112  

An Aging Simulation Model for the Emergency Diesel Generators of Angra 2 by Supplementary Variables

ICONE16-48130  

Electrical Insulation System Degradation Sensors: “Improving Reliability of Power Generation and Distribution”

ICONE16-48135  

Statistical Maintenance Optimization Approach at Bruce Power

ICONE16-48147  

Review of the Primary and Secondary Water Chemistry Operation of Paks Nuclear Power Plant From the Point of View of Lifetime Extension

ICONE16-48156  

Refurbishment of Secondary System and High AVT Water Treatment of Genkai #1 and # 2

ICONE16-48187  

Thermal Cycle Evaluation for Feedwater Heater Out of Service Condition

ICONE16-48189  

Comparision of Wind and Nuclear Power Economics

ICONE16-48263  

The Study of Instrument Channel Precision and Application in Nuclear Power Qinshan Joint Venture Company Limited

ICONE16-48267  

The Commissioning and Operation of Reactor Power Regulation System of CNP650 Unit

ICONE16-48269  

Technical improvement about the field-mounted adjuster in Turbine Island of Qinshan Nuclear Power Plant Phase II

ICONE16-48271  

Turbine control System Malfunction Analysis

ICONE16-48325  

Allowable Load Derivation of Single Angle Members for Small Bore Pipe Supports Welded onto 4-Bolt CEA Plates in APR1400

ICONE16-48331  

The past and the future of horizontal steam generators

ICONE16-48343  

Development of BWR Power Uprate Method Based on ?Heat Balance Shift? Concept

ICONE16-48390  

Analyses of Free Span Oxide Layrers on SG Tubes of NPP Temelin

ICONE16-48394  

Development of General-Purpose Software to Analyze the Static Thermal Characteristic of Nuclear Power Generation System

ICONE16-48395  

Non-linear BWR Stability Analysis

ICONE16-48429  

Analysis of Pressurized Water Reactor with Pinch, Exergy and Thermoeconomic Methods

ICONE16-48432  

New Graphical Methodology for Energy Integration in Nuclear Steam Power Plant

ICONE16-48441  

"Evaluation of Coupling Desalination With PWR Nuclear Power Plant With Pinch, Exergy and Thermoeconomic Analysis"

ICONE16-48454  

Large AC Drives Applications

ICONE16-48467  

An Equipment Reliability Strategy and Maintenance Program for Improving the Reliability of Cranes at Commercial Nuclear Power Facilities

ICONE16-48473  

Low Boron Level Loading Pattern

ICONE16-48512  

Additional Performance Demonstration of VVER Mechanical Plugs

ICONE16-48523  

Cable Aging Assessment and Condition Monitoring Using Line Resonance Analysis (LIRA)

ICONE16-48531  

Thermalhydraulic Analysis of the Steam Generator Design for the 700 MWe Indian Nuclear Power Plant

ICONE16-48545  

Advanced Test Reactor Life Extension Project

ICONE16-48556  

Torsional Health Diagnostics of Critical Rotating Equipment in Power Plants

ICONE16-48561  

Analysis and Strategy of Ageing and Ageing Management for Steam Generator in 300MWe NPP

ICONE16-48568  

Human Factors Verification and Validation: Tecnatom?s Experience

ICONE16-48575  

The tasks of the steam generator operation at Paks NPP connected the licence renewal and the power upgrade

ICONE16-48588  

Technical development for IASCC irradiation experiments at the JMTR

ICONE16-48636  

Leaker-Free Fuel: Is it Possible with Today’s Water Chemistry Practices?

ICONE16-48637  

Seismic Response Analysis of Reactor Coolant Pump in Nuclear Power Plant

ICONE16-48676  

Development of Significance Determination Process in Japan

ICONE16-48688  

Development of an Evaluation Tool of Radiation Dose Rate in Primary Containment Vessel for Hamaoka BWR Plants

ICONE16-48718  

Chiller Condenser Service Water Cooling Valve Maintenance

ICONE16-48730  

Autoregressive Multivariate Analysis of BWR Bistable Flow

ICONE16-48783  

Changes in Fire Damper Testing Requirement to meet the needs of the Nuclear Industry.

ICONE16-48785  

Relational Design Method for New Reactor Licensing

ICONE16-48786  

Vagaries of PRA applications to assessing the risk of plant conditions

ICONE16-48803  

Characteristics of ATR Fugen MOX fuel shearing at Tokai Reprocessing Plant

ICONE16-48808  

Dresden Units 2 and 3 Isolation Condenser Waterhammer Prevention During Restart Operations

ICONE16-48815  

Development of atlas of defects of steam generators heat exchanging tubes of NPPs with WWER and analysis of testing results

ICONE16-48843  

Integrated Facility Assessment Simulation

ICONE16-48883  

Online Station Nuclear Engineer (SNE) Training

ICONE16-48888  

AP1000 Fuel Design and Core Operations

ICONE16-48893  

Removing Outage Barriers

ICONE16-48894  

Development of a Next Generation Canister Sipping System

ICONE16-48903  

Development of Vertical Pump Diagnostic System using Ultrasonic Vibrometer

ICONE16-48904  

Development and Application of Technologies for Maintenance of a Lifetime and Safety the NPP Components

ICONE16-48911  

Overview of EDF Life Cycle Management and Nuclear Asset Management Methodology and Tools

ICONE16-48913  

Fuel Assembly Instrument Tube Tube Tie-Rods

ICONE16-48919  

ACR-1000 Plant Layout

ICONE16-48925  

RFID Applications in Nuclear Power Plants

ICONE16-48938  

Increased Concern for Degradation of Upper Steam Drum Internals Leading to Monitoring and Modifications Considerations

ICONE16-48940  

WARRANTY TEST FOR A HIGH-PRESSURE TURBINE RETROFIT USING PROCESS DATA RECONCILIATION IN ACCORDANCE WITH VDI 2048

ICONE16-48942  

Flow-Induced Vibration Model for Steam Generator Tubes in Two-Phase Flow

ICONE16-48952  

Radiation Protection Technician Two-Year Associates of Applied Science Curriculum for National Implementation

ICONE16-48956  

Development Of Full Scale Reactor Coolant Pump Thrust Bearing Test System And Qualification Process For Retrofit Thrust Bearing Oil Seal With Commercial Grade Components