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In This Volume
Volume 1A: Codes and Standards
Codes and Standards
API 579/ASME Code Fitness-for-Service Activities
R5 Code Based Creep Analysis of a Thick-Wall Cylinder With Steam Film Cooling Hole Structure
PVP 2017; V01AT01A001https://doi.org/10.1115/PVP2017-65475
Topics:
Creep
,
Cylinders
,
Film cooling
,
Steam
,
Cooling
,
Damage
,
Temperature
,
Cooling systems
,
Design
,
Power stations
Fitness-for-Service Assessment of Steam Generator Tubing Subject to Dealloying Degradation
PVP 2017; V01AT01A003https://doi.org/10.1115/PVP2017-66201
Topics:
Boilers
,
Fitness-for-service
,
Tubing
,
Acceptance criteria
,
Alloys
,
Condition monitoring
,
Copper
,
Inspection
,
Life cycle management
,
Nickel
ASME Section XI Code Activities
Technical Basis for ASME Code Section XI Nonmandatory Appendix C Update
PVP 2017; V01AT01A004https://doi.org/10.1115/PVP2017-65058
Topics:
ASME Standards
,
Stress
,
Pipes
,
Cylinders
,
Fracture (Materials)
,
Torsion
,
Boilers
,
Failure mechanisms
,
Flow (Dynamics)
,
Fracture toughness
Fracture Tests of Flat Plate and Pipe With Non-Aligned Multiple Flaws
PVP 2017; V01AT01A008https://doi.org/10.1115/PVP2017-66169
Topics:
Flat plates
,
Fracture (Materials)
,
Fracture (Process)
,
Pipes
,
Ductile fracture
,
Stress
,
Evaluation methods
,
Boilers
,
Collapse
,
Displacement
Large Dataset Assessment of the Upper Shelf Master Curve Model
PVP 2017; V01AT01A010https://doi.org/10.1115/PVP2017-66280
Topics:
Flow (Dynamics)
,
Fracture toughness
,
Scalars
,
Steel
,
Stress
,
Temperature effects
,
Uncertainty
Assessment of Fatigue and Fracture — A Probabilistic Perspective (Maintaining Integrity of Components)
Confidence Bounds for Fatigue Distribution Functions
PVP 2017; V01AT01A011https://doi.org/10.1115/PVP2017-65416
Topics:
Fatigue
,
Uncertainty
,
Fatigue life
,
Reliability
,
Steel
,
Approximation
,
ASTM International
,
Carbon
,
Creep
,
Design
Development of a Novel Test Procedure to Investigate the Impact of Strain Gradients on the Fatigue Endurance of Stainless Steel
PVP 2017; V01AT01A012https://doi.org/10.1115/PVP2017-65496
Topics:
Fatigue
,
Stainless steel
,
Strain gradient
,
Stress
,
Testing
,
Nuclear power stations
,
Design
,
Finite element analysis
,
Membranes
,
Pipes
Assessment of Uncertainty Sources in Fatigue Usage in Relation to Deterministic Margins, and Sensitivity Analysis
PVP 2017; V01AT01A013https://doi.org/10.1115/PVP2017-65850
Topics:
Fatigue
,
Sensitivity analysis
,
Uncertainty
,
Safety
,
Reliability
,
Design
,
ASME Standards
,
Linkages
,
Probability
,
Stress
Environmental Fatigue Issues (Joint With M&F)
Overview of International Implementation of Environmental Fatigue (Update)
PVP 2017; V01AT01A015https://doi.org/10.1115/PVP2017-65006
Topics:
Fatigue
,
Nuclear power stations
,
Water
,
Coolants
,
Fatigue life
,
Testing
Mean Stress Effect on Fatigue Properties of Type 316 Stainless Steel: Part I — In High-Temperature Air Environment
PVP 2017; V01AT01A016https://doi.org/10.1115/PVP2017-65135
Topics:
Fatigue properties
,
High temperature
,
Stainless steel
,
Stress
,
Fatigue life
,
Fracture (Materials)
,
Fatigue testing
INCEFA-PLUS (Increasing Safety in Nuclear Power Plants by Covering Gaps in Environmental Fatigue Assessment)
PVP 2017; V01AT01A018https://doi.org/10.1115/PVP2017-65256
Topics:
Fatigue
,
Nuclear power stations
,
Safety
,
Testing
,
Finishes
,
Databases
,
Stress
,
Workshops (Work spaces)
,
Fatigue damage
,
Fatigue testing
Complex Low-Cycle Fatigue Damage Assessment of Components and Piping of Nuclear Power Plants Type WWER
PVP 2017; V01AT01A019https://doi.org/10.1115/PVP2017-65257
Topics:
Damage assessment
,
Low cycle fatigue
,
Nuclear power stations
,
Pipes
,
Damage
,
Corrosion
,
Design
,
Fatigue
,
Fatigue damage
,
Fatigue design
ASME Code-Case Proposal to Explicitly Quantify the Interaction Between the PWR Environment and Component Surface Finish
PVP 2017; V01AT01A020https://doi.org/10.1115/PVP2017-65367
Topics:
Finishes
,
Pressurized water reactors
,
Fatigue life
,
Polishing
,
Testing
,
Design
,
Fatigue
,
Boiling water reactors
,
Electric arc furnaces
,
Fatigue damage
Further Validation of the Weighted Stress Intensity Factor Rate (WKR) Method for Stainless Steel Pressurised Water Reactor Fatigue Crack Growth Calculations
PVP 2017; V01AT01A024https://doi.org/10.1115/PVP2017-65645
Topics:
Fatigue cracks
,
Stainless steel
,
Stress
,
Water
,
Cycles
,
Fatigue
,
Pressurized water reactors
,
Temperature
,
Thermal shock
,
ASME Boiler and Pressure Vessel Code
Effect of Hold Periods on the Corrosion Fatigue Crack Growth Rates of Austenitic Stainless Steels in LWR Coolant Environments
PVP 2017; V01AT01A025https://doi.org/10.1115/PVP2017-65787
Topics:
Coolants
,
Corrosion
,
Fatigue cracks
,
Light water reactors
,
Stainless steel
,
Fracture (Materials)
,
Stress
,
ASME Standards
,
Fatigue
,
Shapes
Fatigue Modeling of 508 LAS Under Variable Amplitude Loading: A Mechanistic Based Analytical Approach
PVP 2017; V01AT01A026https://doi.org/10.1115/PVP2017-65876
Topics:
Fatigue
,
Modeling
,
Fatigue testing
,
Light water reactors
,
Pressurized water reactors
,
Alloy steel
,
Coolants
,
Parameter estimation
,
Plasticity
,
Safety
Is it Possible to Get-Rid of S-N Curve for Fatigue Evaluation?: A Fully Mechanistic Model of 316SS Reactor Steel for Fatigue Life Evaluation
PVP 2017; V01AT01A027https://doi.org/10.1115/PVP2017-65890
Topics:
Fatigue
,
Fatigue life
,
Steel
,
Stress
,
Hardening
,
Modeling
,
Plasticity
,
Uncertainty
,
Computer software
,
Cycles
An Investigation Into the Lifetimes of Solid and Hollow Fatigue Endurance Specimens Using Cyclic Hardening Material Models in Finite Element Analysis
PVP 2017; V01AT01A028https://doi.org/10.1115/PVP2017-65975
Topics:
Fatigue
,
Finite element analysis
,
Hardening
,
Testing
,
Fatigue life
,
Light water reactors
,
Cycles
,
Geometry
,
Inspection
,
Membranes
Effect of Variable Temperature on the Fatigue Life and Crack Growth Rates of Austenitic Stainless Steels in PWR Coolant Environments
PVP 2017; V01AT01A029https://doi.org/10.1115/PVP2017-66029
Topics:
Coolants
,
Fatigue life
,
Fracture (Materials)
,
Pressurized water reactors
,
Stainless steel
,
Temperature
,
Fatigue
,
Transients (Dynamics)
,
Fatigue cracks
,
Stress
Models for Calculating the Effect of Environment on Fatigue Life (Fen) for Complex Waveforms and/or Non-Isothermal Conditions
PVP 2017; V01AT01A030https://doi.org/10.1115/PVP2017-66030
Topics:
Accounting
,
Coolants
,
Cycles
,
Fatigue
,
Fatigue cracks
,
Fatigue life
,
Nuclear power stations
,
Oxygen
,
Pressurized water reactors
,
Stainless steel
Fatigue With Hold Times Simulating NPP Normal Operation Results for Stainless Steel Grades 304L and 347
PVP 2017; V01AT01A031https://doi.org/10.1115/PVP2017-66097
Topics:
Fatigue
,
Nuclear power stations
,
Stainless steel
,
Fatigue life
,
Alloys
,
Steady state
,
Temperature
,
Transients (Dynamics)
,
Coolants
,
Design
Proposed ASME Code High Cycle Fatigue Design Curves for Austenitic and Ferritic Steels
PVP 2017; V01AT01A035https://doi.org/10.1115/PVP2017-66242
Topics:
ASME Standards
,
Design
,
High cycle fatigue
,
Steel
,
Cycles
,
Stress
,
Fatigue
,
Fatigue design
,
Alloy steel
,
Carbon
Fatigue and Ratcheting Issues in Pressure Vessel and Piping Design
Thermal Stress Ratchet Check in Piping Analysis
PVP 2017; V01AT01A036https://doi.org/10.1115/PVP2017-66008
Topics:
Pipes
,
Thermal stresses
,
Temperature
,
Ambiguity
,
Flat plates
,
Geometry
,
Heat transfer
,
Materials properties
,
Pressure
,
Stress
Comparison of Methods for Structural Stress Determination According to EN 13445-3 Annex NA
PVP 2017; V01AT01A037https://doi.org/10.1115/PVP2017-66112
Topics:
Stress
,
Design
,
Fatigue
,
Pressure vessels
,
Bricks
,
Design methodology
,
Fatigue analysis
,
Fatigue life
,
Finite element analysis
,
Finite element model
Alternative Approaches for ASME Code Simplified Elastic-Plastic Analysis
PVP 2017; V01AT01A038https://doi.org/10.1115/PVP2017-66240
Topics:
ASME Standards
,
Finite element analysis
,
Pipes
,
Stress
,
Alloy steel
,
Alloys
,
Analytical methods
,
Carbon steel
,
Elastic analysis
,
Fatigue
Fatigue Monitoring and Related Assessment Methods
Structural Health Monitoring for Conventional Power Plants: Solutions for Operational Challenges
PVP 2017; V01AT01A040https://doi.org/10.1115/PVP2017-66072
Topics:
Power stations
,
Structural health monitoring
,
Stress
,
Creep
,
Fatigue
,
Damage
,
Design
,
Thermal power stations
,
Fatigue damage
,
High temperature
A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact of Deformable Projectile
PVP 2017; V01AT01A041https://doi.org/10.1115/PVP2017-66090
Topics:
Damage
,
Projectiles
,
Reinforced concrete
,
Impact testing
,
Simulation analysis
,
Simulation results
,
Simulation
A Screening Methodology to Rapidly Reduce ILI Data, Visualise and Determine Most Detrimental Defects in Pipelines
PVP 2017; V01AT01A042https://doi.org/10.1115/PVP2017-66190
Topics:
Pipelines
,
Density
,
Dimensions
,
Finite element analysis
,
Inspection
,
Pipeline risers
,
Rendering
,
Risers (Casting)
,
Visualization
Hydrogen Effects on Material Behavior for Structural Integrity Assessment (Joint With MF-3)
Excellent Resistance to Hydrogen Embrittlement of High-Strength Copper-Based Alloy
PVP 2017; V01AT01A043https://doi.org/10.1115/PVP2017-65532
Topics:
Alloys
,
Copper
,
Hydrogen embrittlement
,
Hydrogen
,
Fracture toughness
,
Tensile strength
,
Annealing
,
Compression
,
Cooling
,
Ductility
Current Status of Evaluation and Selecting of Materials to Be Used for Hydrogen Refueling Station Equipment in Japan
PVP 2017; V01AT01A044https://doi.org/10.1115/PVP2017-66250
Topics:
Hydrogen
,
Containers
,
High pressure (Physics)
,
Pressure
,
Storage
,
Engineering standards
,
Fuel cell vehicles
,
Fuels
,
Governments
,
Safety
Hydrogen Flakes Assessment in the RPVs
ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects
Hilda B. Klasky, B. Richard Bass, Terry L. Dickson, Sarma B. Gorti, Randy K. Nanstad, Mikhail A. Sokolov, William L. Server, Paul T. Williams
PVP 2017; V01AT01A045https://doi.org/10.1115/PVP2017-65305
Structural Integrity Assessment of Doel 3 and Tihange 2 RPVs: ASME B&PV Code Section III Primary Stress Re-Evaluation Accounting for the Presence of Hydrogen Flakes
PVP 2017; V01AT01A046https://doi.org/10.1115/PVP2017-66031
Topics:
Accounting
,
Hydrogen
,
Stress
,
Pressure
,
Reactor vessels
,
Shells
,
Accidents
,
Collapse
,
Density
,
Design
Structural Integrity Assessment of Doel 3 and Tihange 2 RPVs: Fatigue Crack Growth Analysis of Hydrogen Flakes
PVP 2017; V01AT01A047https://doi.org/10.1115/PVP2017-66032
Topics:
Fatigue cracks
,
Hydrogen
,
Shells
,
Reactor vessels
,
Accidents
,
Manufacturing
,
Nuclear power stations
,
Safety
,
Transients (Dynamics)
Improvement of Flaw Characterization Rules in Fitness-for-Service Codes
Integrity of Cast Stainless Steel Pipe
Integrity of Reactor Pressure Vessels and Internals for Codes
Exploratory Analysis to Estimate Axial Fracture Toughness for Zr-2.5Nb Pressure Tubes Using Test Data From Small Curved Compact Specimens
PVP 2017; V01AT01A060https://doi.org/10.1115/PVP2017-66116
Topics:
Fracture toughness
,
Pressure
,
Zirconium
,
Fracture (Materials)
,
Leak-before-break
,
Containment
,
Coolants
,
Electromagnetic scattering
,
Nuclear reactors
,
Testing
Master Curve Fracture Toughness and Other Small Specimen Mechanical Properties (Joint With MF-13)
Embrittlement Trend Curves for Notch and Fracture Toughness of 15Kh2MFAA Type Steel
PVP 2017; V01AT01A063https://doi.org/10.1115/PVP2017-65174
Topics:
Embrittlement
,
Fracture toughness
,
Steel
,
Surveillance
,
Reactor vessels
,
Databases
,
Fluence (Radiation measurement)
,
Temperature effects
,
Vessels
,
Copper
Cost-Effective Alternatives to Conventional Charpy Tests for Measuring the Impact Toughness of Very-High-Toughness Steels
PVP 2017; V01AT01A064https://doi.org/10.1115/PVP2017-65259
Topics:
Fracture toughness
,
Steel
,
Fracture (Materials)
,
Deformation
,
Ductility
,
Electrical discharge machining
,
Fatigue
,
Friction
,
Hammers
,
Impact testing
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