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Volume 1: Codes and Standards
Codes and Standards
ASME Code Section XI Activities
Review of Technical Basis for ASME Code Section XI Appendix L
PVP 2020; V001T01A003https://doi.org/10.1115/PVP2020-21690
Topics:
ASME Standards
,
Fatigue
,
Fracture mechanics
Environmental Fatigue Issues (Joint M&F)
Further Evidence of Margin for Environmental Effects, Termed Fen-Threshold, in the ASME Section III Design Fatigue Curve for Austenitic Stainless Steels Through the Interaction Between the PWR Environment and Surface Finish
PVP 2020; V001T01A013https://doi.org/10.1115/PVP2020-21262
Topics:
Alloys
,
Design
,
Fatigue
,
Finishes
,
Nickel
,
Pressurized water reactors
,
Stainless steel
Strain Control Correction for Fatigue Testing in LWR Environments
Marc Vankeerberghen, Alec Mclennan, Igor Simonovski, German Barrera, Sergio Arrieta Gomez, Miroslava Ernestova, Norman Platts, Marc Scibetta, Marius Twite
PVP 2020; V001T01A014https://doi.org/10.1115/PVP2020-21373
Topics:
Fatigue
,
Fatigue testing
,
Light water reactors
,
Gages
,
Calibration
,
Corrosion
,
Displacement
,
Finite element analysis
,
Fracture (Materials)
,
Half-life
INCEFA-PLUS Project: Review of the Test Programme
Matthias Bruchhausen, Alec McLennan, Roman Cicero, Caitlin Huotilainen, Kevin Mottershead, Jean-Christophe le Roux, Marc Vankeerberghen
PVP 2020; V001T01A015https://doi.org/10.1115/PVP2020-21377
Topics:
Experimental design
,
Fatigue
,
Fatigue life
,
Fatigue testing
,
Light water reactors
,
Nuclear power stations
,
Safety
,
Stainless steel
,
Steel
,
Stress
INCEFA-PLUS Project: The Impact of Using Fatigue Data Generated From Multiple Specimen Geometries on the Outcome of a Regression Analysis
Alec Mclennan, Philippe Spätig, Jean-Christophe Le Roux, Joshua Waters, Peter Gill, Jack Beswick, Norman Platts
PVP 2020; V001T01A017https://doi.org/10.1115/PVP2020-21422
Topics:
Electric arc furnaces
,
Fatigue
,
Performance
,
Regression analysis
Thermo-Mechanical Fatigue Crack Growth Testing
PVP 2020; V001T01A018https://doi.org/10.1115/PVP2020-21424
Topics:
Design
,
Fatigue cracks
,
Testing
,
Thermomechanics
Environmental Fatigue Screening for Subsequent License Renewal
PVP 2020; V001T01A023https://doi.org/10.1115/PVP2020-21678
Topics:
Fatigue
,
Licensing
,
Fatigue analysis
,
Cycles
,
Electric arc furnaces
,
Nuclear reactor coolants
,
Pressure
,
Transients (Dynamics)
,
Water
Recent Argonne National Laboratory Estimated Thermal Expansion Coefficients for Reactor Pressure Boundary Base Metal, Similar and Dissimilar Metal Welds
PVP 2020; V001T01A024https://doi.org/10.1115/PVP2020-21828
Topics:
Base metals
,
Metals
,
Pressure
,
Thermal expansion
,
Welded joints
,
Fillers (Materials)
,
Nuclear reactors
,
Safety
,
Stress
,
Stress analysis (Engineering)
Fatigue and Fracture Assessment and Management: A Probabilistic Perspective
Fatigue Life Modeling Using Nitinol Data
PVP 2020; V001T01A025https://doi.org/10.1115/PVP2020-21752
Topics:
Fatigue life
,
Modeling
,
Nickel titanium alloys
,
Biomedicine
,
Cycles
,
Stents
,
Stress
,
Weibull distribution
,
Blood
,
Failure
An Assessment of Uncertainty in Design Factors and Strain-Rate Inputs for Environmentally-Assisted Fatigue and Related Margins
PVP 2020; V001T01A026https://doi.org/10.1115/PVP2020-21756
Topics:
Design
,
Fatigue
,
Uncertainty
,
Failure
,
Probability
,
Cycles
,
Fatigue design
,
Reliability
,
Stress
,
Nozzles
Fatigue and Ratcheting Issues in Pressure Vessel and Piping Design
Efficient Fatigue and Ratcheting Computation in Case of Multi-Parameter Loading
PVP 2020; V001T01A027https://doi.org/10.1115/PVP2020-21089
Topics:
Computation
,
Fatigue
,
Stress
,
ASME Standards
,
Cycles
,
Cylinders
,
Design
,
Elastic analysis
,
Pressure
,
Shear (Mechanics)
A Historical Overview of Design Analyses and Experimental Observations of Ratcheting Phenomenon
Jean Macedo, Stéphane Chapuliot, Jean-Michel Bergheau, Eric Feulvarch, Olivier Ancelet, Antoine Martin
PVP 2020; V001T01A029https://doi.org/10.1115/PVP2020-21383
Topics:
Constitutive equations
,
Design
,
Kinematics
Investigation Into Methods for Determining Moment Ranges at Piping Tees and Branches
PVP 2020; V001T01A030https://doi.org/10.1115/PVP2020-21632
Topics:
Pipes
,
Stress
,
Piping systems
,
Junctions
,
ASME Boiler and Pressure Vessel Code
,
Fatigue
,
Finite element model
,
Geometry
,
Gravity (Force)
,
Thermal expansion
Fatigue Consideration of Layered Vessels
PVP 2020; V001T01A033https://doi.org/10.1115/PVP2020-21841
Topics:
Fatigue
,
Vessels
,
Pressure vessels
,
Fatigue life
,
ASME Standards
,
Design
,
Manufacturing
,
Shells
,
Vents
,
Bending (Stress)
Fatigue Monitoring and Related Assessment Method
Fracture Toughness and Other Small Specimen Mechanical Properties
General Codes and Standards for Pressure Equipment Overview
Introduction of the Technical Document in Japan for Safety Use of Type2 Pressure Vessels in Hydrogen Refueling Stations
Shinya Sato, Hiroshi Kobayashi, Hajime Fukimoto, Shigeru Maeda, Nobuhiro Yoshikawa, Hironobu Arashima
PVP 2020; V001T01A039https://doi.org/10.1115/PVP2020-21120
Topics:
Hydrogen
,
Pressure vessels
,
Safety
,
Carbon reinforced plastics
,
Design
,
Metals
,
Alloys
,
Fatigue analysis
,
Steel
,
Autofrettage
High Temperature Codes and Standards
Elimination of BWR Mark I Program Primary Containment Drywell-to-Wetwell Differential Pressure
PVP 2020; V001T01A045https://doi.org/10.1115/PVP2020-21001
Topics:
Boiling water reactors
,
Containment
,
Pressure
,
Vents
,
Accidents
,
Nitrogen
,
Water
,
Control rooms
,
Filters
,
Pipes
The Influence of Multiaxial Stress Relaxation on Component Creep Damage Accumulation in Biaxial, Mixed Primary, and Secondary Loading on a Pipe
PVP 2020; V001T01A046https://doi.org/10.1115/PVP2020-21211
Topics:
Creep
,
Damage
,
Pipes
,
Relaxation (Physics)
,
Stress
,
Aeroelasticity
,
Cycles
,
Ductility
,
High temperature
,
Inelastic analysis
Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Vertical and Horizontal Loading
PVP 2020; V001T01A047https://doi.org/10.1115/PVP2020-21328
Topics:
Buckling
,
Evaluation methods
,
Testing
,
Vessels
,
Stress
,
Compression
,
Shear (Mechanics)
,
Steel
,
Design
,
Japan Society of Mechanical Engineers
Codes and Standards for Managing Degradation of Boilers in Service
PVP 2020; V001T01A048https://doi.org/10.1115/PVP2020-21612
Topics:
Boilers
,
Engineering standards
Improvement of Flaw Characterization Rules for FFS
Assessment of Flaw Interaction Under Combined Tensile and Bending Stresses: Suitability of ASME Code Case N877-1
PVP 2020; V001T01A050https://doi.org/10.1115/PVP2020-21452
Topics:
ASME Standards
,
Bending (Stress)
,
Stress
,
Fitness-for-service
,
Membranes
,
Pressure
,
Residual stresses
,
Stress concentration
,
Welding
Master Curve Method and Applications
Post-Irradiation Evaluation of Eurofer97 Fracture Toughness Using Miniature Multinotch Bend Bar Specimens
Xiang Chen, Logan A. Clowers, Tim Graening, Arunodaya Bhattacharya, Anne A. Campbell, Janet Robertson, Josina W. Geringer, Mikhail A. Sokolov, Yutai Katoh, Michael Rieth
PVP 2020; V001T01A059https://doi.org/10.1115/PVP2020-21312
Probabilistic and Risk-Informed Methods for Structural Integrity Assessment
Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP
PVP 2020; V001T01A063https://doi.org/10.1115/PVP2020-21427
Topics:
Fracture mechanics
,
Stress corrosion cracking
,
Water
,
Stress
,
Boiling water reactors
,
Collaboration
,
Failure
,
Fatigue
,
Nuclear power
,
Nuclear power stations
Recent Developments in ASME Codes and Standards
Uncertainty Quantification of Viscoplastic Parameters for Grade 91 Steel Through Bayesian Analysis
PVP 2020; V001T01A066https://doi.org/10.1115/PVP2020-21306
Topics:
Algorithms
,
Calibration
,
Chain
,
Creep
,
Deformation
,
Electromagnetic scattering
,
Engineering design
,
Failure
,
Heat
,
Heat exchangers
Development of Design Method for High Temperature Nuclear Reactor Cladded Components
PVP 2020; V001T01A067https://doi.org/10.1115/PVP2020-21469
Topics:
Design methodology
,
High temperature
,
Nuclear reactors
,
Design
,
Coolants
,
Corrosion resistant materials
,
Corrosion
,
Creep
,
Failure
,
Finite element analysis
Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components
PVP 2020; V001T01A070https://doi.org/10.1115/PVP2020-21493
Topics:
High temperature
,
Nuclear reactors
,
Creep
,
Design
,
Alloys
,
Temperature
,
Cladding systems (Building)
,
Design methodology
,
Elastic moduli
,
Failure
Acceptance Criteria for the Mechanical Integrity of Clad/Base Metal Interface for High Temperature Nuclear Reactor Cladded Components
PVP 2020; V001T01A071https://doi.org/10.1115/PVP2020-21494
Topics:
Acceptance criteria
,
Base metals
,
High temperature
,
Nuclear reactors
,
Design
,
Shear stress
,
Temperature
,
Design methodology
,
Bonding
,
Corrosion resistance
Recent Developments in Chinese Codes and Standards
Inspection Case Analysis of Natural Gas Manifold in a High Acid Gas Field
PVP 2020; V001T01A075https://doi.org/10.1115/PVP2020-21061
Topics:
Inspection
,
Manifolds
,
Natural gas
,
Natural gas fields
Analysis of the Flange Seal Groove Cracking in a Hydrocracking Reactor
PVP 2020; V001T01A081https://doi.org/10.1115/PVP2020-21199
Topics:
Flanges
,
Fracture (Process)
,
Stress
Study on Numerical Simulation of Gas-Solid Erosion for Horizontal Feed Pipe
PVP 2020; V001T01A082https://doi.org/10.1115/PVP2020-21205
Topics:
Computer simulation
,
Erosion
,
Pipes
,
Two-phase flow
Safety Assessment of Pressure Vessels in Service for More Than 20 Years
PVP 2020; V001T01A084https://doi.org/10.1115/PVP2020-21238
Topics:
Pressure vessels
,
Safety
Experimental Investigation on Burst Pressure and Fatigue Life of Type IV LPG Cylinders
PVP 2020; V001T01A086https://doi.org/10.1115/PVP2020-21264
Topics:
Cylinders
,
Fatigue life
,
Pressure
,
Cycles
,
Composite materials
,
Corrosion resistance
,
Design
,
Explosions
,
Fibers
,
Fire
Performance Tests on Gas Storage Wells With/Without Thread Defects
PVP 2020; V001T01A090https://doi.org/10.1115/PVP2020-21370
Topics:
Failure mechanisms
,
Leakage
,
Storage
,
Testing performance
,
Thread
,
Wells
Recent Developments in European Codes and Standards
Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
PVP 2020; V001T01A093https://doi.org/10.1115/PVP2020-21720
Topics:
Compression
,
Creep
,
Design
,
Displacement
,
Engineering standards
,
Fatigue
,
Fatigue testing
,
Generation IV reactors
,
High temperature
,
Sodium
Establishing AMR Structural Integrity Codes and Standards for UK GDA (EASICS): Overview of Activities to Provide Guidance for the UK Generic Design Assessment Process for High Temperature Advanced Modular Reactors
PVP 2020; V001T01A094https://doi.org/10.1115/PVP2020-21721
Topics:
Creep
,
Design
,
Engineering standards
,
Fatigue
,
High temperature
Repair, Replacement, and Mitigation for Fitness-for-Service Rules
Pipeline Crack Half-Life Versus 1.10 Safety Factor at Next Inspection
PVP 2020; V001T01A095https://doi.org/10.1115/PVP2020-21054
Topics:
Fracture (Materials)
,
Half-life
,
Inspection
,
Pipelines
,
Safety
Investigation of Relationship Between Microhardness and Charpy Impact Energy for Temper Bead Welding Qualification: Part 2
PVP 2020; V001T01A096https://doi.org/10.1115/PVP2020-21300
Topics:
Microhardness
,
Welding
,
Heat
,
Alloy steel
,
Heat treating (Metalworking)
,
Maintenance
,
Nuclear industry
,
Optimization
,
Testing
Tempering Efficiency Evaluation for Dissimilar Weld Overlays
Eun Jang, Jeffrey Stewart, Yuxiang Luo, Shijie Qu, Boian Alexandrov, Steven L. McCracken, Jonathan Tatman, Darren Barborak, Jorge A. Penso
PVP 2020; V001T01A098https://doi.org/10.1115/PVP2020-21708
Topics:
Overlays (Materials engineering)
,
Thermocouples
,
Temperature
,
Welding
,
Cycles
,
Heat
,
Alloys
,
Base metals
,
Corrosion
,
Energy generation
A Feasibility Study on Crack Repair in Austenitic Stainless Steel Dry Storage Canisters Using Isothermal Friction Stir Welding
PVP 2020; V001T01A099https://doi.org/10.1115/PVP2020-21716
Topics:
Fracture (Materials)
,
Friction
,
Maintenance
,
Microhardness
,
Stainless steel
,
Storage
,
Welding
,
Plates (structures)
,
Base metals
,
Damage
Structural Integrity of Pressure Components
Strain Limits Against Local Fracture of Vessels and Components
PVP 2020; V001T01A101https://doi.org/10.1115/PVP2020-21028
Topics:
Fracture (Materials)
,
Fracture (Process)
,
Stress
,
Vessels
Residual-Stress, Material Characterization in P22 HRSG-Pipeline Butt Joint
Ottaviano Grisolia, Lorenzo Scano, Francesco Piccini, Antonietta Lo Conte, Massimiliano De Agostinis, Stefano Fini
PVP 2020; V001T01A102https://doi.org/10.1115/PVP2020-21077
Topics:
Creep
,
Heat recovery steam generators
,
Pipelines
,
Stress
,
Welding
,
Aeroelasticity
,
ASTM International
,
Drilling
,
Heating
,
Modeling
Local Failure Analysis of Bolted Flanges
PVP 2020; V001T01A105https://doi.org/10.1115/PVP2020-21569
Topics:
Bolted flanges
,
Damage
,
Design
,
Failure
,
Failure analysis
,
Stress
,
ASME Boiler and Pressure Vessel Code
,
Flanges
,
Pressure
,
Tension
Analysis of HDPE Failure Data in Support of Development of Flaw Acceptance Criteria for Butt Fusion Joints
PVP 2020; V001T01A107https://doi.org/10.1115/PVP2020-21783
Topics:
Acceptance criteria
,
Failure data
,
Stress
,
Pipes
,
Failure
,
Temperature
,
Density
,
Fracture (Materials)
,
Inspection
,
Safety
Total Life Reliability Methods
Probabilistic Leak Before Break Using the R6 Methodology
PVP 2020; V001T01A110https://doi.org/10.1115/PVP2020-21769
Topics:
Leak-before-break
,
Stress
,
Computer software
,
Failure
,
Probability
,
Reliability
,
Fracture (Materials)
,
Fracture mechanics
,
Inspection
,
Leakage
Very High Cycle Fatigue Behavior
Investigation of the Very High Cycle Fatigue (VHCF) Behavior of Austenitic Stainless Steels and Their Welds for Reactor Internals at Ambient Temperature and 300°C
PVP 2020; V001T01A112https://doi.org/10.1115/PVP2020-21460
Topics:
Fatigue
,
High cycle fatigue
,
Stainless steel
,
Temperature
,
Welded joints
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