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Proceedings Papers
18th International Conference on Nuclear Engineering: Volume 5
Component Reliability and Materials Issues
Applicability Study of Computed Radiography to NDE for Piping and Component in Nuclear Power Plant
ICONE 2010; 87-91https://doi.org/10.1115/ICONE18-29215
Topics:
Nondestructive evaluation
,
Nuclear power stations
,
Pipes
,
X-rays
,
Imaging
,
Noise (Sound)
,
Testing
,
Biomedicine
,
Filters
,
Inspection
Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor
ICONE 2010; 97-102https://doi.org/10.1115/ICONE18-29269
Topics:
Boiling water reactors
,
Stress
,
Irradiation (Radiation exposure)
,
Stress corrosion cracking
,
Neutrons
,
Temperature
,
Accidents
,
Carbon
,
Corrosion
,
Cycles
Multiphysics Modeling and Simulation for Stress Corrosion Cracking Considering Oxygen Atom Diffusion Along Grain Boundary
ICONE 2010; 129-133https://doi.org/10.1115/ICONE18-29337
Topics:
Atoms
,
Diffusion (Physics)
,
Grain boundaries
,
Modeling
,
Oxygen
,
Simulation
,
Stress corrosion cracking
,
Fracture (Materials)
,
Crack propagation
,
Stress
The Effect of Fabrication Process on Microstructure Evolution of N18 Alloy Sheets
ICONE 2010; 135-140https://doi.org/10.1115/ICONE18-29339
Topics:
Alloys
,
Manufacturing
,
Hot rolling
,
Recrystallization
,
Texture (Materials)
,
Cold rolling
,
Deformation
,
Density
,
Annealing
,
Electron backscatter diffraction
The Reliability Analysis of Bearing in Large Blower System
ICONE 2010; 157-163https://doi.org/10.1115/ICONE18-29391
Topics:
Bearings
,
Event history analysis
,
Reliability
Parameters Influencing the Secondary Hydrogenation of Zr-Sn and Zr-Nb Alloys During Steam Oxidation Under LOCA and Severe Accident Conditions
ICONE 2010; 165-171https://doi.org/10.1115/ICONE18-29405
Topics:
Accidents
,
Alloys
,
Oxidation
,
Steam
,
Tin
,
Zirconium
,
Hydrogen
,
Cladding systems (Building)
,
Gas flow
,
Temperature
Quality Control of Interface Between Tungsten Coating and Cu Alloy Heat Sink of PFC for EAST Tokamak by Infrared Thermography
ICONE 2010; 173-178https://doi.org/10.1115/ICONE18-29435
Topics:
Coating processes
,
Coatings
,
Copper alloys
,
Heat sinks
,
Quality control
,
Thermography
,
Tokamaks
,
Tungsten
,
Nondestructive evaluation
,
Testing
Study on the Hydrogen Effect on the Temper Embrittlement of 2.25Cr-1Mo Steel
ICONE 2010; 179-184https://doi.org/10.1115/ICONE18-29503
Topics:
Embrittlement
,
Hydrogen
,
Steel
,
Grain boundaries
,
Hydrogen embrittlement
,
Testing
,
Augers
,
Electrons
The Mechanical Properties and Friction and Wear Behavior of C/C-SIC
ICONE 2010; 185-190https://doi.org/10.1115/ICONE18-29705
Topics:
Friction
,
Mechanical properties
,
Wear
,
Composite materials
,
Carbon
,
Stress
,
Silicon
,
Water
,
Carbon fibers
,
Scanning electron microscopy
Chemico-Physical Causes of Radiation-Induced “Long Cell” Action Corrosion in Water Cooled Reactors
ICONE 2010; 191-206https://doi.org/10.1115/ICONE18-29714
Topics:
Corrosion
,
Radiation (Physics)
,
Water
,
Fittings
,
Electrochemistry
,
Electrons
,
Boiling water reactors
,
Chemical potential
,
Chemistry
,
Cooling systems
Aspects of Minimizing Steel Corrosion in Liquid Lead-Alloys by Addition of Oxygen
ICONE 2010; 207-218https://doi.org/10.1115/ICONE18-29726
Topics:
Lead alloys
,
Oxygen
,
Steel corrosion
,
Sensors
,
Liquid metals
,
Steel
,
Testing
Development of Electrical Resistivity Measurement Systems for Inspecting Void Swelling in Irradiated Microscopy Discs
ICONE 2010; 223-228https://doi.org/10.1115/ICONE18-29893
Topics:
Disks
,
Electrical resistivity
,
Measurement systems
,
Microscopy
,
Radiation (Physics)
,
Alloys
,
Carbon
,
Precipitation
,
Test facilities
,
Titanium
Proactive Aging Management: PAM 2.0
ICONE 2010; 275-281https://doi.org/10.1115/ICONE18-30094
Topics:
China
,
Computer software
,
Condition monitoring
,
Engineers
,
Maintenance
,
Nuclear power stations
,
Reliability
,
Safety
,
Teaching
Irradiation-Induced Embrittlement of INCONEL 600 Flux Detectors in CANDU Reactors
ICONE 2010; 293-298https://doi.org/10.1115/ICONE18-30121
Topics:
Embrittlement
,
Irradiation (Radiation exposure)
,
Sensors
,
Temperature
,
Wire
,
Failure
,
Corrosion
,
Design
,
Cables
,
Heat
An Accurate Probabilistic Model for Estimating the Life Cycle Cost of Degrading Components in Nuclear Power Plants
ICONE 2010; 299-308https://doi.org/10.1115/ICONE18-30130
Topics:
Life cycle costing
,
Nuclear power stations
,
Maintenance
,
Optimization
,
Cycles
,
Failure
,
Inspection
,
Reliability
,
Risk
,
Safety
Application of Extra High Purity Austenitic Stainless Steel to Weld Overlay
ICONE 2010; 317-322https://doi.org/10.1115/ICONE18-30197
Topics:
Overlays (Materials engineering)
,
Stainless steel
,
Alloys
,
Corrosion
,
Metals
,
Fracture (Materials)
,
Boiling
,
Corrosion resistance
,
High temperature
,
Ions
Pressurized Water Reactor Core Crud Mapping
ICONE 2010; 333-339https://doi.org/10.1115/ICONE18-30218
Topics:
Boiling
,
Chemistry
,
Computers
,
Coolants
,
Corrosion
,
Fuels
,
Manufacturing
,
Pressurized water reactors
,
Radiation (Physics)
,
Risk
Bruce Power Aging Obsolescence Program
ICONE 2010; 347-356https://doi.org/10.1115/ICONE18-30249
Topics:
Failure
,
Heat exchangers
,
Maintenance
,
Pipes
,
Reliability
,
Resolution (Optics)
Introduction of Hot Isostatically Pressed, Reactor Coolant System Components in PWR Plant
ICONE 2010; 357-367https://doi.org/10.1115/ICONE18-30253
Topics:
Bonding
,
Design
,
Inspection
,
Leakage
,
Manufacturing
,
Mechanical properties
,
Mechanical testing
,
Nuclear reactor coolants
,
Nuclear reactors
,
Pressure
Steam Generator Ageing Management Database
ICONE 2010; 375-378https://doi.org/10.1115/ICONE18-30279
Topics:
Boilers
,
Databases
,
Nuclear power stations
,
Reliability
,
Safety
,
Data acquisition
,
Data centers
,
Engineers
,
Steam
,
Stress corrosion cracking
Development of a Large Diameter Electromagnetic Pump for 4S
ICONE 2010; 387-392https://doi.org/10.1115/ICONE18-30374
Topics:
Pumps
,
Sodium
,
Flow (Dynamics)
,
Flowmeters
,
Design
,
Maintenance
,
Calibration
,
Control systems
,
Engineering prototypes
,
Flow instability
Structural Integrity
Numerical Evaluation of Fluctuating Pressure at Stub Pipes in Actual BWR Main Steam Lines
ICONE 2010; 463-468https://doi.org/10.1115/ICONE18-29355
Topics:
Boiling water reactors
,
Pipes
,
Pressure
,
Steam
,
Resonance
,
Acoustics
,
Fluctuations (Physics)
,
Nuclear power stations
,
Power uprate
,
Evaluation methods
Fluctuating Pressure Generating in BWR Main Steam Lines Acoustic Excited by Safety Relief Valve Stub Pipes and Dead Legs
Shiro Takahashi, Keita Okuyama, Akinori Tamura, Masaya Ohtsuka, Masaaki Tsubaki, Mabuchi Yasuhiro, Teppei Kubota, Yukio Ogawa, Fumio Inada, Ryo Morita
ICONE 2010; 469-478https://doi.org/10.1115/ICONE18-29361
Topics:
Acoustics
,
Boiling water reactors
,
Pipes
,
Pressure
,
Relief valves
,
Safety
,
Steam
,
Resonance
,
Flow (Dynamics)
,
Finite element methods
Quantitative Evaluation of Hydrogen Micro-Damage in 316L Austenitic Stainless Steel
ICONE 2010; 505-515https://doi.org/10.1115/ICONE18-29462
Topics:
Damage
,
Hydrogen
,
Stainless steel
,
Fracture (Process)
,
Microscale devices
,
Embrittlement
,
Fractography
,
Geometry
,
Hydrogen embrittlement
,
Surface roughness
Development and Demonstration of a New Testing Capability for Simulating Multiple Fuel Assembly Impact During a Seismic Event
ICONE 2010; 517-522https://doi.org/10.1115/ICONE18-29468
Topics:
Earthquakes
,
Fuels
,
Manufacturing
,
Testing
,
Engineering prototypes
,
Pendulums
,
Deformation
,
Displacement
,
Mechanical testing
,
Model development
Experimental and Numerical Simulation of Radiolysis Gas Detonations and Mechanical Response of BWR Exhaust Pipes
ICONE 2010; 529-537https://doi.org/10.1115/ICONE18-29697
Topics:
Boiling water reactors
,
Computer simulation
,
Exhaust systems
,
Explosions
,
Steam
,
Pipes
,
Pressure
,
Valves
,
Condensation
,
Damage
Dynamic Analysis of Including New Loads on Spent Fuel Storage Rack
ICONE 2010; 549-552https://doi.org/10.1115/ICONE18-29721
Topics:
Dynamic analysis
,
Spent fuel storage
,
Stress
,
Safety
,
Accidents
,
Coolants
,
Degrees of freedom
,
Fuels
,
Regulations
,
Relief valves
Effect of Hydrogen Isotope and Concentration on Delayed Hydride Crack Growth Rates in Zr-2.5Nb Pressure Tubes
ICONE 2010; 559-569https://doi.org/10.1115/ICONE18-29786
Topics:
Fracture (Materials)
,
Hydrogen
,
Isotopes
,
Pressure
,
Zirconium
,
Temperature
,
Fracture (Process)
,
Cracking (Materials)
,
Diffusion (Physics)
,
Leakage
PCI Risk Assessment Model
ICONE 2010; 585-591https://doi.org/10.1115/ICONE18-29838
Topics:
Cladding systems (Building)
,
Failure
,
Fuels
,
Monitoring systems
,
Pressure
,
Pressurized water reactors
,
Probability
,
Risk
,
Risk assessment
,
Temperature
The Effect of Load Reduction on Crack Initiation Behavior of Hydrides From Flaws in Zr-2.5Nb Pressure Tube Material
ICONE 2010; 597-606https://doi.org/10.1115/ICONE18-29880
Topics:
Fracture (Materials)
,
Pressure
,
Stress
,
Zirconium
,
Fracture (Process)
,
Hydrogen
,
Alloys
,
Diffusion (Physics)
,
Finite element analysis
,
Nuclear reactors
Dynamic Response of a Nuclear Power Plant Subjected to External Accident Event
ICONE 2010; 607-615https://doi.org/10.1115/ICONE18-29896
Topics:
Accidents
,
Dynamic response
,
Nuclear power stations
,
Design
,
Containment
,
Safety
,
Aircraft
,
Containment systems
,
Finite element methods
,
Finite element model
Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA
ICONE 2010; 671-677https://doi.org/10.1115/ICONE18-30189
Topics:
Boiling water reactors
,
Finite element analysis
,
Power uprate
,
Structural dynamics
,
Containment
,
Dynamic analysis
,
Fluids
,
Reactor vessels
,
Safety
,
Stress