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Proceedings Papers
In This Volume
Volume 1: Codes and Standards
Codes and Standards
Structural Integrity of Pressure Components
Elastic-Plastic Analysis According to 2007 Section VIII-Div.2 Rules
Fatigue Analysis Methods: Their Performance Evaluation for a Class of Pressure Vessels With Welded Joints
PVP 2009; 69-77https://doi.org/10.1115/PVP2009-77859
Topics:
Fatigue analysis
,
Performance evaluation
,
Pressure vessels
,
Welded joints
,
Cycles
,
Vessels
,
Carbon steel
,
Flat plates
,
Pressure
Ratcheting Issues in Pressure Vessel Design
Ratcheting Predictive Methods in RCC-MR Code
PVP 2009; 89-94https://doi.org/10.1115/PVP2009-77766
Topics:
Construction
,
Cycles
,
Damage
,
Design
,
Drainage
,
High temperature
,
Membranes
,
Pipes
,
Risk
,
Shells
Residual Stress and Strain Responses of Welded Piping Joints Under Low-Cycle Fatigue Loading
PVP 2009; 95-101https://doi.org/10.1115/PVP2009-77813
Topics:
Low cycle fatigue
,
Pipe joints
,
Stress
,
Fatigue failure
,
Residual stresses
,
Simulation
,
Welded joints
,
Finite element analysis
,
Welding
,
Fatigue
Simulation of Ratcheting Responses of Elbow Piping Components
PVP 2009; 103-108https://doi.org/10.1115/PVP2009-77819
Topics:
Pipes
,
Simulation
,
Collapse
,
Damage
,
Failure
,
Stress
,
Deflection
,
Design
,
Earthquakes
,
Fatigue
Environmental Fatigue Issues
Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation Method for Nuclear Power Plant in JSME Code
PVP 2009; 123-132https://doi.org/10.1115/PVP2009-77077
Topics:
Evaluation methods
,
Fatigue
,
JSME Standards
,
Nuclear power stations
,
Light water reactors
,
Nuclear power
,
Coolants
,
Electrohydrodynamics
,
Fatigue life
,
Safety
Comparison of Component Fatigue Test Data With Proposed EAF Methodologies for Austenitic Stainless Steel
PVP 2009; 153-162https://doi.org/10.1115/PVP2009-78124
Topics:
Electric arc furnaces
,
Fatigue testing
,
Stainless steel
,
Fatigue
,
Fatigue life
,
Design
,
Licensing
,
ASME Standards
,
Cycles
,
Light water reactors
Interaction and Flaw Modeling for Multiple Flaws
Fracture Assessment of Austenitic Stainless Steel Piping With Twin Flaws in TIG Weld
PVP 2009; 215-221https://doi.org/10.1115/PVP2009-77717
Topics:
Fracture (Materials)
,
Pipes
,
Stainless steel
,
Stress
,
Fracture (Process)
,
Boiling water reactors
,
Electrical discharge machining
,
Base metals
,
Failure
,
Metals
API 579/ASME Code Fitness-for-Service Activities
ASME Code Section XI Activities
Assessment of Piping Field Failures and Burst Tests on Carbon Steel Pipes With Local Wall Thinning Using ASME Section XI Code Case N-597-2
PVP 2009; 297-305https://doi.org/10.1115/PVP2009-77132
Topics:
Carbon steel
,
Failure
,
Pipes
,
Corrosion
,
Flow (Dynamics)
,
Rupture
,
ASME Boiler and Pressure Vessel Code
,
Erosion
,
Fracture (Materials)
,
Fracture (Process)
Recent Developments in ASME Codes and Standards
ASME B31.12 Hydrogen Piping and Pipeline Code Design Rules and Their Interaction With Pipeline Materials Concerns, Issues and Research
PVP 2009; 355-361https://doi.org/10.1115/PVP2009-77159
Topics:
Design
,
Hydrogen
,
Pipelines
,
Pipes
,
Steel
,
Chemistry
,
Design methodology
,
Industrial research
,
Pipeline systems
,
Piping systems
Recent Developments in Korean and Japanese Codes and Standards
Evaluation of Fracture Characteristics of Ni-Base Weld Metal for BWR Components
PVP 2009; 419-427https://doi.org/10.1115/PVP2009-77720
Topics:
Boiling water reactors
,
Fracture (Materials)
,
Fracture (Process)
,
Metals
,
Stress
,
Alloys
,
Ductile fracture
,
Flow (Dynamics)
,
Fracture toughness
,
Temperature
Recent Developments in Chinese Codes and Standards
Recent Developments in European and International Codes and Standards
Presentation of RCC-MR Code 2007 for High Temperature Reactor and ITER Projects: Improvement of the Leak-Before-Break Procedure and Related Defect Assessment Tools
PVP 2009; 501-510https://doi.org/10.1115/PVP2009-77119
Topics:
High temperature
,
Leak-before-break
,
Fracture mechanics
,
Construction
,
Creep
,
Fracture (Materials)
,
Pipes
,
Plates (structures)
,
Stress
Cross Comparison of European and American Pressure Vessel Standards in the Design of the Main Pressure Vessel Components
PVP 2009; 519-529https://doi.org/10.1115/PVP2009-77273
Topics:
Design
,
Pressure vessels
,
Manufacturing
,
Cylinders
,
Engineering standards
,
Flanges
,
Inspection
,
Shapes
,
Stress
,
Testing
Strength Assessment of Equipments and Piping of WWER Nuclear Power Plants
PVP 2009; 537-541https://doi.org/10.1115/PVP2009-77919
Topics:
Nuclear power stations
,
Pipes
,
Stress
,
Fatigue
,
ASME Standards
,
Collapse
,
Corrosion
,
Design
,
Mechanical engineers
,
Nozzles
BS 7910: History and Future Developments
PVP 2009; 555-563https://doi.org/10.1115/PVP2009-78057
Topics:
Corrosion
,
Creep
,
Design
,
Failure
,
Fatigue
,
Fracture (Materials)
,
Maintenance
,
Manufacturing
,
Ocean engineering
,
Pipelines
High Temperature Codes and Standards
Presentation of RCC-MR Code 2007 for High Temperature Reactor and ITER Projects: Improvement of the Creep Fatigue Rules
PVP 2009; 567-572https://doi.org/10.1115/PVP2009-77120
Topics:
Creep
,
Fatigue
,
High temperature
,
Cycles
,
Stress
,
Temperature
,
Sodium fast reactors
,
Construction
,
Damage
,
Gas cooled reactors
A Comparative Study of Negligible Creep Curves for Rational Elevated Temperature Design
PVP 2009; 573-582https://doi.org/10.1115/PVP2009-77232
Topics:
Creep
,
Design
,
Temperature
,
Materials properties
,
Steel
,
Stainless steel
,
Damage
,
Fast neutron reactors
,
Ferrites (Magnetic materials)
,
Sodium fast reactors
Recent Developments in High Temperature Codes
PVP 2009; 603-612https://doi.org/10.1115/PVP2009-78130
Topics:
High temperature
,
Design
,
Engineering standards
,
Creep
,
Damage
,
Fatigue
,
Power stations
,
Service life (Equipment)
Repair, Replacement and Mitigation for Fitness-for-Service Rules
Stress Corrosion Cracking in Welds of Reactor Vessel Nozzle at Ohi-3 and of Other Vessel’s Nozzle at Japan’s PWR Plants
PVP 2009; 629-637https://doi.org/10.1115/PVP2009-77344
Topics:
Alloys
,
Maintenance
,
Nozzles
,
Pressurized water reactors
,
Reactor vessels
,
Stress corrosion cracking
,
Welded joints
Development of Stress Reduction Method in the Pipe Welded Zone
PVP 2009; 639-645https://doi.org/10.1115/PVP2009-77901
Topics:
Pipes
,
Stress
,
Tension
,
Stainless steel
,
Carbon
,
Compressive stress
,
Countermeasures
,
Failure
,
Ice
,
Water
Probabilistic and Risk Based Assessment for Codes and Standards
Validity of Successive Inspections to the Piping With Multiple Circumferential Stress Corrosion Cracks
PVP 2009; 649-655https://doi.org/10.1115/PVP2009-77186
Topics:
Corrosion
,
Fracture (Materials)
,
Hoop stress
,
Inspection
,
Pipes
,
Failure
,
Stress corrosion cracking
,
Boiling water reactors
,
Fitness-for-service
,
Probability
Innovative Concepts for Next Generation Codes and Standards
Methodology for the Determination of a Set of Safety Factors That are Consistent for Design Code and Fitness-for-Service Code: Framework
PVP 2009; 697-704https://doi.org/10.1115/PVP2009-77333
Topics:
Design
,
Fitness-for-service
,
Safety
,
Reliability
,
Construction
,
Japan Society of Mechanical Engineers
,
Light water reactors
,
Nuclear reactors
,
Pipes
,
Pressure
Methodology for the Determination of a Set of Safety Factors That are Consistent for Design Code and Fitness-for-Service Code: Case Study for Fast Breeder Reactors
PVP 2009; 705-710https://doi.org/10.1115/PVP2009-77686
Topics:
Breeder reactors
,
Design
,
Fitness-for-service
,
Safety
,
Stress
,
Failure mechanisms
,
Fracture (Materials)
,
Reliability
,
Creep
,
Fatigue
Materials, Welding, Design, and Residual Life of Czech A.M.E. Codes
VERLIFE: Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation—Updating and Further Development
PVP 2009; 745-750https://doi.org/10.1115/PVP2009-77392
Topics:
Nuclear power stations
,
Pipes
,
Reactor vessels
,
Design
,
Failure
,
Fatigue
,
Fracture mechanics
,
Leak-before-break
,
Pressurized water reactors
,
Risk
Safety Approach and Ageing Management in Czech Rules and Standards
PVP 2009; 755-761https://doi.org/10.1115/PVP2009-77653
Topics:
Safety
,
Failure
,
Nuclear power stations
,
Design
,
Maintenance
,
Pipes
,
Manufacturing
,
Accidents
,
Boundary-value problems
,
Cooling
Structural Integrity of Fusion Reactor Components
Qualification of Cryogenic Structural Materials for the ITER Toroidal Field Coils
PVP 2009; 789-797https://doi.org/10.1115/PVP2009-77553
Topics:
Carbon
,
Forgings (Products)
,
Helium
,
Mass production
,
Nitrogen
,
Plates (structures)
,
Quality control
,
Stainless steel
,
Temperature
,
Temperature effects
Plenary Session
Calvin W. Rice Lecture
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