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Proceedings Papers
Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management
Plant Operations, Maintenance and Life Cycle
Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048
ICONE 2006; 7-14https://doi.org/10.1115/ICONE14-89025
Topics:
Boilers
,
Boiling water reactors
,
Calibration
,
Certainty
,
Design
,
Emergencies
,
Errors
,
Heat
,
Instrumentation
,
Nuclear power stations
Main Generator Seal Oil Supply Reliability Improvements at Southern California Edison’s San Onofre Nuclear Generating Station
ICONE 2006; 15-21https://doi.org/10.1115/ICONE14-89086
Topics:
Generators
,
Power stations
,
Reliability
,
Bearings
,
Lubrication
,
Turbogenerators
,
Turbines
,
Damage
,
Failure
,
Lubricating oils
WWER Steam Generators Tubing Performance and Aging Management
Nikolay B. Trunov, Stanislav E. Davidenko, Vladimir A. Grigoriev, Valery S. Popadchuk, Sergey I. Brykov, Georgy P. Karzov
ICONE 2006; 31-39https://doi.org/10.1115/ICONE14-89096
Topics:
Boilers
,
Tubing
,
Nuclear power stations
,
Corrosion
,
Heat
,
Condition monitoring
,
Damage
,
Databases
,
Design
,
Eddies (Fluid dynamics)
BWR Steam Dryer for Extended Power Uprate
Yann Le Moigne, Anders Andre´n, Ingemar Greis, Hans Kornfeldt, Per Sundlo¨f, Jan Sjunnesson, Anna-Karin Karlsson
ICONE 2006; 133-138https://doi.org/10.1115/ICONE14-89301
Topics:
Boiling water reactors
,
Power uprate
,
Steam
,
Design
,
Computational fluid dynamics
,
Dryers
,
Flow (Dynamics)
,
Nozzles
,
Performance characterization
,
Vibration
A Method to Quantify Plant Availability and Initiating Event Frequency Using a Large Event Tree, Small Fault Tree Model
ICONE 2006; 149-157https://doi.org/10.1115/ICONE14-89321
Topics:
Damage
,
Maintenance
,
Modeling
,
Optimization
,
Probabilistic risk assessment
,
Risk management
,
Systems engineering
Advanced Pipe Replacement Procedure for a Defective CRDM Housing Nozzle Enables Continued Normal Operation of a Nuclear Power Plant
ICONE 2006; 159-168https://doi.org/10.1115/ICONE14-89326
Topics:
Nozzles
,
Nuclear power stations
,
Pipes
,
Maintenance
,
Robots
,
Training programs
,
Computer numerical control machine tools
,
Contamination
,
Cutting
,
Finishing
New Design of a Digital CRCS by Introducing LOM
ICONE 2006; 179-186https://doi.org/10.1115/ICONE14-89444
Topics:
Computers
,
Control equipment
,
Control systems
,
Design
,
Maintenance
,
Nuclear power stations
,
Nuclear reactions
,
Power converters
,
Reliability
,
Signals
An Integrated Simulator for the Maintenance Optimization of Light Water Reactors
Shinobu Yoshimura, Kazuo Furuta, Yoshihiro Isobe, Mitsuyuki Sagisaka, Michiyasu Noda, Tetsuya Wada, Hiroshi Akiba
ICONE 2006; 187-194https://doi.org/10.1115/ICONE14-89475
Topics:
Light water reactors
,
Maintenance
,
Optimization
,
Fracture mechanics
,
Nuclear power
,
Nuclear power stations
,
Piping systems
,
Risk
,
Safety
Use of a Best Estimate Power Monitoring Tool to Maximize Power Plant Generation
ICONE 2006; 195-203https://doi.org/10.1115/ICONE14-89543
Topics:
Computation
,
Computers
,
Condensed matter
,
Exhaust systems
,
Failure
,
Feedwater
,
Flow (Dynamics)
,
Flowmeters
,
High pressure (Physics)
,
Instrumentation
Aging and Plant Life Management with the Software Tool COMSY
ICONE 2006; 211-218https://doi.org/10.1115/ICONE14-89597
Topics:
Computer software
,
Inspection
,
Nuclear power stations
,
Corrosion
,
Damage
,
Fatigue
,
Feedback
,
In-service inspection
,
Maintenance
,
Optimization
Measuring the Cost of Obsolescence
ICONE 2006; 249-252https://doi.org/10.1115/ICONE14-89680
Topics:
Engineering instruments
,
Failure
,
Irradiation (Radiation exposure)
,
Maintenance
,
Nuclear fuels
,
Nuclear power stations
,
Performance
,
Risk
,
Safety
,
Testing
INSREC: Computational System for Quantitative Analysis of Radiation Effects Covering All Radiation Field
Dong Hoon Shin, Young Wook Lee, Young Ho Cho, Hyun Seok Ko, SukHoon Kim, YongMin Kim, Chang Sun Kang
ICONE 2006; 277-283https://doi.org/10.1115/ICONE14-89724
Topics:
Radiation (Physics)
,
Radiation effects
,
Databases
,
Accidents
,
Nuclear power
,
Nuclear power stations
,
Reliability
,
Diffusion (Physics)
,
Errors
,
Expert systems
Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Load Reduction
ICONE 2006; 327-332https://doi.org/10.1115/ICONE14-89903
Topics:
Acoustics
,
Steam
,
Stress
,
Power uprate
,
Valves
,
Vibration
,
Dryers
,
Pipes
,
Safety
,
Sound pressure
Component Reliability and Materials Issues
Tribocorrosion in PWR: A Parametric Approach
ICONE 2006; 333-339https://doi.org/10.1115/ICONE14-89013
Topics:
Pressurized water reactors
,
Stainless steel
,
Wear
,
High temperature
,
Hydrogen
,
Kinematics
,
Pressure
,
Tribometers
,
Water
,
Water chemistry
Corrosion Behaviour Inconel 617 in VHTR Environment
ICONE 2006; 341-347https://doi.org/10.1115/ICONE14-89014
Topics:
Cooling
,
Corrosion
,
Damage
,
Gas cooled reactors
,
Graphite
,
Leakage
,
Very high temperature reactors
The Application of Structural Materials Data From the BN-350 Fast Reactor to Life Extension of Light Water Reactors
O. G. Romanenko, S. B. Kislitsin, O. P. Maksimkin, Sh. B. Shiganakov, Ye. V. Chumakov, I. V. Dumchev
ICONE 2006; 349-359https://doi.org/10.1115/ICONE14-89028
Topics:
Fast neutron reactors
,
Life extension
,
Light water reactors
,
Steel
,
Tensile strength
,
Yield strength
,
Breeder reactors
,
Damage
,
Ductility
,
Elongation
Bolted Flanged Connection for Critical Plant/Piping Systems
ICONE 2006; 361-369https://doi.org/10.1115/ICONE14-89045
Topics:
Flange connections
,
Piping systems
,
Design
,
Flanges
,
Gaskets
,
Operating temperature
,
Pipe joints
,
Pressure
,
Shape memory alloys
The OECD Pipe Failure Data Exchange Project: Validation of Canadian Data
ICONE 2006; 389-400https://doi.org/10.1115/ICONE14-89176
Topics:
Failure data
,
Pipes
,
Failure
,
Databases
,
Nondestructive evaluation
,
Feedback
,
Industrial research
,
In-service inspection
,
Leak-before-break
,
Nuclear power
Ligament Rupture Pressure of Fretted SG Tubes of PWRs
ICONE 2006; 415-418https://doi.org/10.1115/ICONE14-89211
Topics:
Pressure
,
Pressurized water reactors
,
Rupture
,
Fracture (Materials)
,
Fracture (Process)
,
Boilers
,
High pressure (Physics)
,
Pumps
,
Safety
,
Temperature
Development and Application of Laser Peening System for PWR Power Plants
Masaki Yoda, Itaru Chida, Satoshi Okada, Makoto Ochiai, Yuji Sano, Naruhiko Mukai, Gaku Komotori, Ryoichi Saeki, Toshimitsu Takagi, Masanori Sugihara, Hirokata Yoriki
ICONE 2006; 419-424https://doi.org/10.1115/ICONE14-89228
Topics:
Laser hardening
,
Lasers
,
Power stations
,
Pressurized water reactors
,
Ultrasonic testing
SCC Propagation Rate of Type 304, 304L Steels Under Oceanic Air Environment
ICONE 2006; 443-450https://doi.org/10.1115/ICONE14-89271
Topics:
Concretes
,
Corrosion
,
Electromagnetic scattering
,
Glass
,
Radiation scattering
,
Scattering (Physics)
,
Spent fuel storage
,
Stainless steel
,
Steel
,
Storage
Identification of CSSC Caused by Ageing and Degradation
ICONE 2006; 451-456https://doi.org/10.1115/ICONE14-89286
Topics:
Accidents
,
Databases
,
Design
,
Failure
,
Maintenance
,
Modeling
,
Nuclear power stations
,
Optimization
,
Reliability
,
Risk
Development of Residual Stress Improvement for Nuclear Pressure Vessel Instrumentation Nozzle Weld Joint (P-43+P-8) by Means of Induction Heating
ICONE 2006; 467-476https://doi.org/10.1115/ICONE14-89297
Topics:
Alloys
,
Electromagnetic induction
,
Heating
,
Instrumentation
,
Iron
,
Nickel
,
Nozzles
,
Reactor vessels
,
Stainless steel
,
Stress
Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components (II)
ICONE 2006; 491-494https://doi.org/10.1115/ICONE14-89346
Topics:
Cladding systems (Building)
,
Lasers
,
Welding
,
Laser welding
,
Shapes
,
Maintenance
,
Reliability
,
Stress corrosion cracking
“Long-Cell Action” Corrosion: A Basic Mechanism Hidden Behind Components Degradation Issues in Nuclear Power Plants
ICONE 2006; 495-511https://doi.org/10.1115/ICONE14-89350
Topics:
Corrosion
,
Nuclear power stations
,
Batteries
,
Coolants
,
Electrochemical cells
,
Electrochemical reactions
,
Electrodes
,
Electrons
,
Erosion
,
Flow (Dynamics)
Electroslag Strip Cladding of Steam Generators With Alloy 690
ICONE 2006; 539-545https://doi.org/10.1115/ICONE14-89434
Topics:
Alloys
,
Boilers
,
Cladding systems (Building)
,
Strips
,
Welding
,
Base metals
,
Cracking (Materials)
,
Filler metals
,
Fracture (Process)
,
Heat
Statistical Analyses for Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Building a Master Curve on an Extract of the “Euro” Fracture Toughness Dataset, Controlling Statistical Uncertainty for Both Mono-Temperature and Multi-Temperature Tests
ICONE 2006; 553-561https://doi.org/10.1115/ICONE14-89481
Risk-Informed Assessment of Degraded Containment Vessels
ICONE 2006; 569-578https://doi.org/10.1115/ICONE14-89499
Topics:
Containment vessels
,
Risk
,
Corrosion
,
Nuclear power stations
,
Risk analysis
,
Shells
,
Steel
,
Structural analysis
Environmental Qualification of an Actuator Torque Switch
ICONE 2006; 579-585https://doi.org/10.1115/ICONE14-89520
Topics:
Actuators
,
Switches
,
Torque
,
Accidents
,
Containment
,
Steam
,
Testing
,
Contact resistance
,
Coolants
,
Cycles
The Lead-Alloy Corrosion Study at KAERI
ICONE 2006; 601-606https://doi.org/10.1115/ICONE14-89600
Topics:
Corrosion
,
Lead alloys
,
Construction
,
Coolants
,
Conceptual design
,
Fast neutron reactors
,
Hybrid power systems
,
Liquid metals
,
Nuclear fission
,
Nuclear power
A Review of the Effects of Elevated Temperature on Concrete Materials and Structures
ICONE 2006; 615-624https://doi.org/10.1115/ICONE14-89631
Topics:
Concretes
,
Temperature
,
Design
,
Safety
,
Accidents
,
Cements (Adhesives)
,
Composite materials
,
Engineering standards
,
Gases
,
Nuclear power stations
Factors to Be Considered for Selection and Design of Rupture Disc
ICONE 2006; 625-630https://doi.org/10.1115/ICONE14-89634
Topics:
Design
,
Disks
,
Rupture
,
Rupture discs
A Root Cause Study on AOA-PWR and CDA-VVER: A Point of View of “Long-Cell Action” Corrosion Mechanism
ICONE 2006; 631-640https://doi.org/10.1115/ICONE14-89658
Topics:
Corrosion
,
Pressurized water reactors
,
Nickel
,
Erosion
,
Iron
,
Ferrites (Magnetic materials)
,
Flow (Dynamics)
,
Boiling
,
Boron
,
Cycles
Modelling of Irradiated Materials
ICONE 2006; 645-652https://doi.org/10.1115/ICONE14-89685
Topics:
Modeling
,
Atoms
,
Dislocations
,
Particulate matter
,
Collisions (Physics)
,
Damage
,
Ductility
,
Dynamics (Mechanics)
,
Hardening
,
Ions
Codes, Standards, Licensing and Regulatory Issues
Update to Risk-Informed Pressurized Water Reactor Vessel 10 to 20 Year Inspection Interval Extension
ICONE 2006; 735-744https://doi.org/10.1115/ICONE14-89470
Topics:
Inspection
,
Pressurized water reactors
,
Reactor vessels
,
Risk
,
Vessels
,
Combustion engineering
,
Design
,
In-service inspection
,
Risk-based inspection
,
Steam
New French Regulation for NPPs and Code Consequences
ICONE 2006; 745-749https://doi.org/10.1115/ICONE14-89616
Topics:
Nuclear power stations
,
Pressure equipment
,
Design
,
Leak-before-break
,
Manufacturing
,
Radiation (Physics)
,
Risk
,
Safety
Reformation of Regulatory Technical Standards for Nuclear Power Generation Equipments in Japan
Mikio Kurihara, Masahiro Aoki, Yu Maruyama, Kiyosi Takasaka, Shigetada Nakajo, Zenichi Ogiso, Yukinori Goto
ICONE 2006; 765-773https://doi.org/10.1115/ICONE14-89707
Topics:
Engineering standards
,
Nuclear power
,
Construction
,
Safety
,
Design
,
Innovation
,
Nuclear power stations
,
Regulations
Consensus Based Nuclear Public-Hearing System Model
Young Wook Lee, Suk Hoon Kim, Young Ho Cho, Hyun Seok Ko, Dong Hoon Shin, Joo Hyun Moon, Chang Sun Kang
ICONE 2006; 775-781https://doi.org/10.1115/ICONE14-89722
Topics:
Construction
,
Decision making
,
Feedback
,
Governments
,
Nuclear industry
,
Reflection
,
Valuation
,
Weight (Mass)
Globalization of ASME Nuclear Codes and Standards
ICONE 2006; 791-794https://doi.org/10.1115/ICONE14-89778
Topics:
Engineering standards
,
ASME Standards
,
Regulations
,
Accreditation
,
China
,
Mechanical engineers
,
Nuclear industry
,
Quality control
,
Safety
Fuel Cycle and High Level Waste Management
Instantaneous Leakage Evaluation of Metal Cask at Drop Impact
ICONE 2006; 815-821https://doi.org/10.1115/ICONE14-89136
Topics:
Leakage
,
Metals
,
Helium
,
Accidents
,
Storage
,
Displacement
,
Gaskets
,
Radiation (Physics)
,
Reinforced concrete
Flowsheet Analysis of U-Pu Co-Crystallization Process as a New Reprocessing System
Shunji Homma, Jun-Ichi Ishii, Jiro Koga, Shiro Matsumoto, Toshiaki Kikuchi, Takahiro Chikazawa, Atsuhiro Shibata
ICONE 2006; 823-828https://doi.org/10.1115/ICONE14-89196
Topics:
Crystallization
,
Decontamination
,
Spent nuclear fuels
,
Crystals
,
Fuels
,
Light water reactors
,
Oxidation
,
Recycling
,
Separation (Technology)
,
Temperature
Transient Thermo-Hydraulic Analysis of the Windowless Target System for the Lead Bismuth Eutectic Cooled Accelerator Driven System
ICONE 2006; 829-838https://doi.org/10.1115/ICONE14-89212
Topics:
Accidents
,
Chain
,
Damage
,
Neutron sources
,
Neutrons
,
Nuclear fission
,
Proton beams
,
Protons
,
Pumps
,
Thermomechanics
Development of Crystallizer for Advanced Aqueous Reprocessing Process
ICONE 2006; 849-855https://doi.org/10.1115/ICONE14-89292
Topics:
Crystallization
,
Cycles
,
Design
,
Fuels
,
Nuclear power
,
Safety
,
Spent nuclear fuels
,
Uranium
Measurement of Atmospheric Sea Salt Concentration in the Dry Storage Facility of the Spent Nuclear Fuel
ICONE 2006; 857-863https://doi.org/10.1115/ICONE14-89293
Topics:
Seas
,
Spent nuclear fuels
,
Storage
,
Concretes
,
Metals
,
Particulate matter
,
Heat
,
Cooling
,
Japan Society of Mechanical Engineers
,
Nuclear power stations
Vitrification Technology Development Plan in Tokai Reprocessing Plant
ICONE 2006; 913-921https://doi.org/10.1115/ICONE14-89430
Topics:
Technology development
,
Vitrification
,
Metals
,
Damage
,
Electrodes
,
Glass
BWR Fuel Thermomechanical Evaluation for Preconditioning Procedures With FEMAXI-V
ICONE 2006; 923-928https://doi.org/10.1115/ICONE14-89506
Topics:
Boiling water reactors
,
Fuels
,
Thermomechanics
,
Failure
,
Cladding systems (Building)
,
Computation
,
Cycles
,
Fuel rods
,
Manufacturing
,
Nuclear power stations
Natural Cooling System Design and Forced Draft Test for Highly Radioactive Vitrified Waste Packages Storage Pits
Isamu Ono, Masaki Jinba, Akira Ono, Kiyoyuki Nagai, Yoshiyuki Kaku, Tetsuro Okubo, Yoshitaka Mino, Masamichi Miyakawa
ICONE 2006; 971-979https://doi.org/10.1115/ICONE14-89813
Topics:
Cooling systems
,
Design
,
Storage
,
Cooling
,
Flow (Dynamics)
,
Construction
,
Drag (Fluid dynamics)
,
Inspection
,
Pressure
,
Viscosity
Room at the Mountain: Estimated Maximum Amounts of Commerical Spent Nuclear Fuel Capable of Disposal in a Yucca Mountain Repository
John H. Kessler, Michael J. Apted, Wei Zhou, John Kemeny, Fraser King, Alan M. Ross, Benjamen Ross, Franklin W. Schwartz
ICONE 2006; 981-990https://doi.org/10.1115/ICONE14-89857
Topics:
Spent nuclear fuels
,
Design
,
High temperature