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In This Volume
Volume 1: Codes and Standards
Front Matter
Codes and Standards
ASME Code Section XI Activities
High Temperature Flaw Evaluation Code Case: Technical Basis and Examples
PVP 2022; V001T01A001https://doi.org/10.1115/PVP2022-85957
Topics:
High temperature
,
Fracture (Materials)
,
Creep
,
Rupture
,
Stress
,
Failure
,
Reliability
,
Simulation
,
Thermomechanics
Code Assessments of Beyond Design Basis Events
Case Study of Probability of Loss of Containment Due to Overpressure
PVP 2022; V001T01A002https://doi.org/10.1115/PVP2022-84710
Topics:
American Petroleum Institute
,
Containment
,
Probability
,
Risk
,
Rupture
Constraint Effects on Codes and Standards
Developments in HDPE and Non-Metallic Pipe Codes and Standards
Design of an Intelligent Butt-Fusing Welding Machine for HDPE Pipes
PVP 2022; V001T01A005https://doi.org/10.1115/PVP2022-84456
Topics:
Design
,
Machinery
,
Pipes
,
Reliability
,
Welding
Comparison of Technical Standards Between Buried and Above Ground Polyethylene Pipe in the Application of Nuclear Power Plant
PVP 2022; V001T01A006https://doi.org/10.1115/PVP2022-84477
Topics:
Design
,
Design methodology
,
Engineering standards
,
Nuclear power stations
,
Pipes
,
Polyethylene pipes
,
Stress
,
Water
,
Cooling
,
Pipelines
Technical Basis for Proposed Code Case on Evaluation of Flaws in Butt Fusion Joints in Class 3 High Density Polyethylene Piping
PVP 2022; V001T01A008https://doi.org/10.1115/PVP2022-84835
Topics:
Density
,
Polyethylene pipes
,
Stress
,
Pipes
,
Acceptance criteria
,
Failure
,
Inspection
,
Safety
,
Temperature
Environmental Fatigue Issues (Joint M&F)
EPR Piping Material Study: Basic Characterization and Low Cycle Fatigue at Room Temperature
PVP 2022; V001T01A010https://doi.org/10.1115/PVP2022-84007
Topics:
Fatigue
,
Low cycle fatigue
,
Pipes
,
Stainless steel
,
Temperature
,
Design
,
Cycles
,
Engineering standards
,
High cycle fatigue
,
Risk-based inspection
The Development of a New Method to Compare the Fatigue Crack Growth Rates of Austenitic Stainless Steel Operating in a PWR Primary Coolant Subjected to Plant Realistic Temperature Loading
PVP 2022; V001T01A011https://doi.org/10.1115/PVP2022-84208
Topics:
Coolants
,
Fatigue
,
Fatigue cracks
,
Pressurized water reactors
,
Stainless steel
,
Temperature
Environment Assisted Fatigue – Experimental Challenges and Solutions
PVP 2022; V001T01A015https://doi.org/10.1115/PVP2022-84719
Topics:
Fatigue
Fatigue and Fracture Assessment and Management – A Probabilistic Perspective
Fatigue-Life Prediction and Design for Uncracked and Cracked Components: Deterministic, A- and B-Basis Probabilistic, and Reliability Target Approaches
PVP 2022; V001T01A016https://doi.org/10.1115/PVP2022-84851
Topics:
Design
,
Failure
,
Fatigue
,
Fatigue life
,
Fracture (Materials)
,
Glass
,
Modeling
,
Nondestructive evaluation
,
Pipes
,
Pressure vessels
An Assessment of the Significance of Design Factors in CUF-Based Fatigue Performance and Related Margins
PVP 2022; V001T01A017https://doi.org/10.1115/PVP2022-84994
Topics:
Design
,
Fatigue
,
Uncertainty
,
Stress
,
Uncertainty quantification
,
Decision making
,
Engineering standards
,
Fracture (Materials)
,
Modeling
,
Sensitivity analysis
Fatigue and Ratcheting Issues in Pressure Vessel and Piping Design
Fatigue Monitoring and Related Assessment Method
CPS – an Advanced Tool for Monitoring Fatigue and Fracture on Pipes and Other Mechanical Components
PVP 2022; V001T01A022https://doi.org/10.1115/PVP2022-84753
Topics:
Fatigue
,
Fracture (Materials)
,
Pipes
,
Stress
,
Monitoring systems
,
Computer software
,
Economics
,
Fracture mechanics
,
Nondestructive evaluation
,
Power stations
Inverse Conduction Method for Complex Thermal Loading
PVP 2022; V001T01A024https://doi.org/10.1115/PVP2022-84913
Topics:
Fatigue
,
Heat conduction
,
Temperature
,
Fracture (Materials)
,
Instrumentation
,
Flow (Dynamics)
,
Stress
,
Thermocouples
,
Transfer functions
,
Algorithms
Fracture Toughness and Other Small Specimen Mechanical Properties (Joint MF-11)
Practical Procedure of Test Temperature Selection for Mini-C(T) Master Curve Evaluation
PVP 2022; V001T01A025https://doi.org/10.1115/PVP2022-82754
Topics:
Reactor vessels
,
Steel
,
Temperature
,
Testing
,
Low temperature
,
Plasticity
,
Surveillance
,
ASTM International
,
Fracture toughness
,
Reliability
High Temperature Codes and Standards
Extrapolation of High Temperature Material Properties of Inconel 617 for Molten Chloride Reactor Experiment Applications
PVP 2022; V001T01A028https://doi.org/10.1115/PVP2022-82286
Topics:
Alloys
,
ASME Boiler and Pressure Vessel Code
,
ASME Standards
,
Boilers
,
Cobalt
,
Corrosion
,
Creep
,
Design
,
Fatigue
,
High temperature
Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading
PVP 2022; V001T01A032https://doi.org/10.1115/PVP2022-84605
Topics:
Buckling
,
Evaluation methods
,
Fast neutron reactors
,
Stainless steel
,
Testing
,
Vessels
,
Steel
,
Stress
,
Design
,
Power stations
Hydrogen Effects on Material Behavior for Structural Integrity Assessment (Joint MF-2)
Improvement of Flaw Characterization Rules for FFS
Failure Bending Stresses for Small Diameter Thick-Wall Pipes
PVP 2022; V001T01A035https://doi.org/10.1115/PVP2022-84598
Topics:
Bending (Stress)
,
Collapse
,
Failure
,
Pipes
,
Stainless steel
,
Stress
3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds
PVP 2022; V001T01A036https://doi.org/10.1115/PVP2022-84667
Topics:
Metals
,
Simulation
,
Stress corrosion cracking
,
Tolerance analysis
,
Water
,
Welded joints
,
Stress
,
Fracture (Materials)
,
Accounting
,
Alloys
International Session for Fast Reactor Design and Construction
Adaptation of Standards to Innovative Reactors
PVP 2022; V001T01A041https://doi.org/10.1115/PVP2022-85479
Topics:
Construction
,
Design
,
Engineering standards
,
Feedback
,
Fusion reactors
,
High temperature
,
Small modular reactors
Master Curve Method and Applications
Development of a Technical Basis for Code Case N-914, “Accounting for the Effect of Embrittlement on Fracture Toughness Properties Used in Evaluations of Pressure Boundary Materials in Class 1 Ferritic Steel Components, Section XI, Division 1”
PVP 2022; V001T01A045https://doi.org/10.1115/PVP2022-83909
Topics:
Accounting
,
Embrittlement
,
Fracture toughness
,
Pressure
,
Reactor vessels
,
Steel
Validation of the Models in ASME CC N-830-1
PVP 2022; V001T01A046https://doi.org/10.1115/PVP2022-83921
Development of Generic Unirradiated Values of T0 and RTTo for Use in ASME Code Applications
PVP 2022; V001T01A047https://doi.org/10.1115/PVP2022-84048
Topics:
Accounting
,
ASME Standards
,
ASTM International
,
Embrittlement
,
Fracture toughness
,
Heat
,
Pressure
,
Reactor vessels
,
Steel
,
Temperature
Probabilistic and Risk-Informed Methods for Structural Integrity Assessment
Can Inservice Inspections Be Eliminated for Passive Components in the U.S. Nuclear Fleet?
PVP 2022; V001T01A050https://doi.org/10.1115/PVP2022-78318
Topics:
In-service inspection
,
Inspection
,
Risk
,
Safety
,
Failure
,
Pipes
,
Risk assessment
,
Vessels
Probabilistic Structural Integrity Analysis for Advanced Modular Reactors
PVP 2022; V001T01A051https://doi.org/10.1115/PVP2022-81135
Topics:
Creep
,
Damage
,
Design
,
Emissions
,
High temperature
,
Nuclear reactors
,
Reliability
,
Robustness
,
Safety
,
Uncertainty
Direct Method-Based Probabilistic Structural Integrity Assessment for High-Temperature Components Considering Uncertain Load Conditions
PVP 2022; V001T01A053https://doi.org/10.1115/PVP2022-84423
Topics:
Event history analysis
,
Failure mechanisms
,
High temperature
,
Stress
,
Reliability
,
Creep
,
Design
,
Failure
,
Fatigue
,
Safety
Data-Centric Structural Integrity Assessment and Risk-Informed Asset Management Using Operational Data and Probabilistic Updating
PVP 2022; V001T01A054https://doi.org/10.1115/PVP2022-84526
Topics:
Risk
,
Engineering standards
,
Design
,
Geometry
,
High temperature
,
In-service inspection
,
Inspection
,
Maintenance
,
Nuclear decommissioning
,
Numerical analysis
Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor
PVP 2022; V001T01A055https://doi.org/10.1115/PVP2022-84742
Topics:
Atoms
,
Bricks
,
Carbon
,
Dimensions
,
Emissions
,
Failure
,
Failure analysis
,
Finite element analysis
,
Fluence (Radiation measurement)
,
Fuels
Recent Developments in ASME Codes and Standards
Implementing Probabilistic Design Methods in Plant Systems Design
PVP 2022; V001T01A061https://doi.org/10.1115/PVP2022-84743
Topics:
Cycles
,
Design
,
Design methodology
,
Failure mechanisms
Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach
PVP 2022; V001T01A062https://doi.org/10.1115/PVP2022-84807
Topics:
Creep
,
Damage
,
Design
,
Fatigue
,
High temperature
,
Alloys
,
Design methodology
,
Failure data
,
Fatigue damage
,
Nuclear reactors
Nickel Cladded Structural Components for Advanced Reactors
PVP 2022; V001T01A063https://doi.org/10.1115/PVP2022-84811
Topics:
Nickel
,
Structural elements (Construction)
,
Design
,
Creep
,
Fatigue
,
High temperature
,
ASME Standards
,
Corrosion
,
Molten salt reactors
,
Base metals
A Viscoplastic Model for Alloy 800H for Use With the Section III, Division 5 Design by Inelastic Analysis Methods for Class A Components
PVP 2022; V001T01A064https://doi.org/10.1115/PVP2022-84861
Topics:
Alloys
,
Design
,
Inelastic analysis
,
Constitutive equations
,
ASME Standards
,
Boilers
,
Calibration
,
Databases
,
Hardening
,
High temperature
Technical Basis of the Code Case Providing Design Rules for the Use of Polyethylene Pipe for Class 3 ASME BPVC Section III, Division 1 Above Ground Piping Systems
PVP 2022; V001T01A065https://doi.org/10.1115/PVP2022-86019
Topics:
ASME Boiler and Pressure Vessel Code
,
Design
,
Piping systems
,
Polyethylene pipes
,
Density
,
Pipes
,
Stress
,
Water
,
Buckling
,
Cooling
Technical Overview and Basis of the Design Sections of the NM.1 Standard
PVP 2022; V001T01A066https://doi.org/10.1115/PVP2022-86021
Topics:
Design
,
Pressure pipes
,
Resins
,
Glass fibers
,
Pressure
,
Springs
Recent Developments in Chinese Codes and Standards
Review on Non-Metallic Pressure Vessels for Cryogenic Applications
PVP 2022; V001T01A067https://doi.org/10.1115/PVP2022-83990
Topics:
Failure
,
Pressure vessels
Recent Developments in European Codes and Standards
Repair, Replacement, and Mitigation for Fitness-for-Service Rules
Revision of Case N-666-1 to Permit Overlay Repair of Dissimilar Metal Socket Welds and to Allow Higher Carbon Content in the Pipe and Socket Fitting
PVP 2022; V001T01A077https://doi.org/10.1115/PVP2022-83798
Topics:
Carbon
,
Fittings
,
Maintenance
,
Metals
,
Overlays (Materials engineering)
,
Pipes
,
Welded joints
,
Leakage
,
Energy generation
,
Failure
Development of the Technical Basis for the New Code Case “Performance and Qualification Criteria for Mitigation of Stress Corrosion Cracking by Surface Stress Improvement”
Nicholas Mohr, Stephen Tate, Marc Albert, Sungwoo Cho, Won-Geun Yi, Jean Collin, Markus Burkardt, John Broussard, Young Sik Pyun
PVP 2022; V001T01A080https://doi.org/10.1115/PVP2022-85151
Topics:
Laser hardening
,
Nanocrystals
,
Plasticity
,
Stress
,
Stress corrosion cracking
Structural Integrity of Pressure Components
Criteria for Specifying Static Equipment Construction Code for Process Plant
PVP 2022; V001T01A081https://doi.org/10.1115/PVP2022-78987
Topics:
Construction
,
Design
,
Temperature
,
Corrosion
,
Heat exchangers
,
Pressure vessels
,
Regulations
,
Safety
,
Weight (Mass)
Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles
PVP 2022; V001T01A082https://doi.org/10.1115/PVP2022-79529
Topics:
Metals
,
Nozzles
,
Reactor vessels
,
Residual stresses
,
Stress
,
Welding
,
Heat
,
Simulation
,
Welded joints
,
Alloys
State-of-the-Art of WPS in RPV PTS Analysis
Maksym Zarazovskii, Vladislav Pištora, Dana Lauerova, Florian Obermeier, Diego Fernando Mora Mendez, Yaroslav Dubyk, Tobias Bolinder, Carlos Cueto-Felgueroso Garcia, Szabolcs Szávai, Judit Dudra, Oriol Costa Garrido, Christophe Blain, Markku Puustinen, Jinya Katsuyama, B. Richard Bass, Paul T. Williams, Oleksii Shugailo
PVP 2022; V001T01A083https://doi.org/10.1115/PVP2022-83699
Topics:
Brittle fracture
,
Ductile fracture
,
Fracture (Materials)
,
Fracture toughness
,
Heat
,
Reactor vessels
,
Steel
,
Stress
,
Thermal shock
,
Transients (Dynamics)
Design of Ellipsoidal and Torispherical Heads in Pressure Vessel and Review of Restrictions in Material Strength Imposed in ASME Sec. VIII Div. 1: A Comparative Study of Various Codes of Constructions
PVP 2022; V001T01A085https://doi.org/10.1115/PVP2022-84770
Topics:
Design
,
Pressure vessels
,
Shapes
,
Strength (Materials)
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