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Proceedings Papers

Proceedings Volume Cover
ASME 2020 Pressure Vessels & Piping Conference
August 3, 2020
Virtual, Online
Conference Sponsors:
  • Pressure Vessels and Piping Division
ISBN:
978-0-7918-8381-5
Volume 1: Codes and Standards

Codes and Standards

ASME Code Section XI Activities

Application of Nickel Electroplating for PWR Reactor Pressure Vessel Cladding Repair
Seong Sik Hwang, Dong Jin Kim
PVP 2020; V001T01A001https://doi.org/10.1115/PVP2020-21051
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Topics: Alloys , Cladding systems (Building) , Maintenance , Nickel plating , Pressurized water reactors , Reactor vessels , Stainless steel , Steel
Comparison of Stress Intensity Factor Coefficients for Plates and Cylinders Under Membrane Stress
Darrell R. Lee, Russell C. Cipolla, Michael C. Liu
PVP 2020; V001T01A002https://doi.org/10.1115/PVP2020-21438
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Topics: Cylinders , Membranes , Plates (structures) , Stress
Review of Technical Basis for ASME Code Section XI Appendix L
Deepak S. Somasundaram, Dilip Dedhia, Do Jun Shim, Gary L. Stevens, Steven X. Xu
PVP 2020; V001T01A003https://doi.org/10.1115/PVP2020-21690
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Topics: ASME Standards , Fatigue , Fracture mechanics
Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds
Amanda Jenks, Warren H. Bamford
PVP 2020; V001T01A004https://doi.org/10.1115/PVP2020-21711
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Topics: Alloys , Fracture (Materials) , Stress corrosion cracking , Welded joints
Application of ASME Code Section XI Appendix L Using 3-D Finite Element Analyses
Charles Fourcade, Minji Fong, James Axline, Do Jun Shim, Chris Lohse, Charles Tomes, Mohammed Farooq
PVP 2020; V001T01A005https://doi.org/10.1115/PVP2020-21729
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Topics: ASME Standards , Fatigue , Finite element analysis

Environmental Fatigue Issues (Joint M&F)

Use of Average Temperature in Fen Calculations
W. F. Weitze
PVP 2020; V001T01A006https://doi.org/10.1115/PVP2020-21009
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Topics: Electric arc furnaces , Fatigue , Temperature , Fatigue damage , Water
Fatigue Benchmark Comparison Effort Between Code_Aster and CNNC/NPIC Software: Part 2
Hai Xie, Zichen Kong, Xuejiao Shao, Tanguy Mathieu, Furui Xiong
PVP 2020; V001T01A007https://doi.org/10.1115/PVP2020-21043
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Topics: Computer software , Fatigue , Algorithms , Electric arc furnaces , Stainless steel , Alloys , Fatigue design , Nickel , Nuclear power stations , Pressurized water reactors
Fatigue Performance of Austenitic Stainless Steel: Enforced Endurance Limit and Questionable Design Curve
Jussi Solin, Tommi Seppänen, Wolfgang Mayinger
PVP 2020; V001T01A008https://doi.org/10.1115/PVP2020-21050
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Topics: Design , Endurance limit , Fatigue , High cycle fatigue , Stainless steel
Study on Incorporation of New Design Fatigue Curves and a New Environmental Fatigue Correction Factor for PWR Environment Into the JSME Environmental Fatigue Evaluation Method
Seiji Asada, Shengde Zhang, Masahiro Takanashi, Yuichiro Nomura
PVP 2020; V001T01A009https://doi.org/10.1115/PVP2020-21078
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Topics: Design , Evaluation methods , Fatigue , Japan Society of Mechanical Engineers , Pressurized water reactors , Stainless steel , Base metals , Fatigue analysis , Metals , Fatigue testing
INCEFA-PLUS Project: Lessons Learned From the Project Data and Impact on Existing Fatigue Assessment Procedures
Sam Cuvilliez, Alec McLennan, Kevin Mottershead, Jonathan Mann, Matthias Bruchhausen
PVP 2020; V001T01A010https://doi.org/10.1115/PVP2020-21106
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Topics: Fatigue , Finishes , Pressurized water reactors
Grade and Temperature Dependent Reference Curves for Realistic Fen Quantification of Austenitic Stainless Steels
Tommi Seppänen, Jouni Alhainen, Esko Arilahti, Jussi Solin
PVP 2020; V001T01A011https://doi.org/10.1115/PVP2020-21136
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Topics: Fatigue , Stainless steel , Temperature
INCEFA-PLUS: Increasing Safety in NPPs by Covering Gaps in Environmental Fatigue Assessment
Kevin Mottershead, Matthias Bruchhausen, Sergio Cicero, Sam Cuvilliez
PVP 2020; V001T01A012https://doi.org/10.1115/PVP2020-21220
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Topics: Fatigue , Nuclear power stations , Safety
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
Alec McLennan, Andrew Morley, Sam Cuvilliez
PVP 2020; V001T01A013https://doi.org/10.1115/PVP2020-21262
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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
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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
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Topics: Experimental design , Fatigue , Fatigue life , Fatigue testing , Light water reactors , Nuclear power stations , Safety , Stainless steel , Steel , Stress
Results From Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels
Ben Coult, Adam Griffiths, Jack Beswick, Peter Gill, Norman Platts, Jean Smith, Gary Stevens
PVP 2020; V001T01A016https://doi.org/10.1115/PVP2020-21406
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Topics: Fatigue testing , Fracture (Materials) , Stainless steel , Testing , Fatigue , Nucleation (Physics) , Stress , Analytical methods , ASME Standards , Bridges (Structures)
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
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Topics: Electric arc furnaces , Fatigue , Performance , Regression analysis
Thermo-Mechanical Fatigue Crack Growth Testing
Jennifer Borg, Norman Platts, Peter Gill, Jonathan Mann, Chris Currie
PVP 2020; V001T01A018https://doi.org/10.1115/PVP2020-21424
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Topics: Design , Fatigue cracks , Testing , Thermomechanics
Codes, Standards, Rules and Assumptions on Environment Assisted Fatigue for Fatigue Management of Primary Piping
Jussi Solin, Tommi Seppänen, Rami Vanninen, Erkki Pulkkinen, Petri Lemettinen, Claude Faidy
PVP 2020; V001T01A019https://doi.org/10.1115/PVP2020-21501
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Topics: Electric arc furnaces , Fatigue , Pipes
Method for Comparison of Different Material Types in Environmental Fatigue Screening
Mark A. Gray, Jamie L. Oakman, Adam P. Walker
PVP 2020; V001T01A020https://doi.org/10.1115/PVP2020-21560
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Topics: Electric arc furnaces , Fatigue , Licensing
Further Development of Fatigue Crack Growth Expressions for Austenitic Stainless Steels in PWR Water and Additional Validation of the WTKR Method
Jonathan Mann, Chris Currie, Jennifer Borg, Norman Platts
PVP 2020; V001T01A021https://doi.org/10.1115/PVP2020-21585
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Topics: Fatigue cracks , Pressurized water reactors , Stainless steel , Water
Investigation Into Crack Closure Effects for Fatigue Crack Growth Under Negative R Conditions
Ben Pellereau, Chris Currie, Jonathan Mann, Ben Coult
PVP 2020; V001T01A022https://doi.org/10.1115/PVP2020-21627
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Topics: Fatigue cracks , Fracture (Materials) , Stress , Testing , Corners (Structural elements) , Pressurized water reactors , Stainless steel , Water
Environmental Fatigue Screening for Subsequent License Renewal
Adam P. Walker, Gregory M. Imbrogno, Mark A. Gray, Charles A. Tomes
PVP 2020; V001T01A023https://doi.org/10.1115/PVP2020-21678
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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
Subhasish Mohanty, Joseph Listwan
PVP 2020; V001T01A024https://doi.org/10.1115/PVP2020-21828
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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
D. Gary Harlow
PVP 2020; V001T01A025https://doi.org/10.1115/PVP2020-21752
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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
Y. S. Garud
PVP 2020; V001T01A026https://doi.org/10.1115/PVP2020-21756
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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
Bastian Vollrath, Hartwig Hübel
PVP 2020; V001T01A027https://doi.org/10.1115/PVP2020-21089
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Topics: Computation , Fatigue , Stress , ASME Standards , Cycles , Cylinders , Design , Elastic analysis , Pressure , Shear (Mechanics)
Critical Review of ASME III Plasticity Correction Factors for Fatigue Design-by-Analysis of Nuclear Power Plant Components
David M. Clarkson, Christopher D. Bell, Donald Mackenzie
PVP 2020; V001T01A028https://doi.org/10.1115/PVP2020-21267
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Topics: Design , Fatigue , Nuclear power stations , Plasticity , Finite element analysis , Electric arc furnaces , Engineering standards , Fatigue analysis , Nuclear industry , Pressure
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
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Topics: Constitutive equations , Design , Kinematics
Investigation Into Methods for Determining Moment Ranges at Piping Tees and Branches
Ben Pellereau, David Candler
PVP 2020; V001T01A030https://doi.org/10.1115/PVP2020-21632
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Topics: Pipes , Stress , Piping systems , Junctions , ASME Boiler and Pressure Vessel Code , Fatigue , Finite element model , Geometry , Gravity (Force) , Thermal expansion
Mode I Ductile Crack Growth of 1TC(T) Specimen Under Large Cyclic Loading: Part IV
Kiminobu Hojo
PVP 2020; V001T01A031https://doi.org/10.1115/PVP2020-21658
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Topics: Ductile fracture , Stress , Fitness-for-service , Fracture (Materials) , Japan Society of Mechanical Engineers , Fatigue cracks , Hardening , Pipes , Computational methods , Computer simulation
Mean Stress Correction of S45C Carbon Steel Based on Crack Growth Concept
Masayuki Kamaya
PVP 2020; V001T01A032https://doi.org/10.1115/PVP2020-21822
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Topics: Carbon steel , Fatigue life , Fatigue limit , Fracture (Materials) , Stress
Fatigue Consideration of Layered Vessels
Kang Xu, Mahendra Rana, Maan Jawad
PVP 2020; V001T01A033https://doi.org/10.1115/PVP2020-21841
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Topics: Fatigue , Vessels , Pressure vessels , Fatigue life , ASME Standards , Design , Manufacturing , Shells , Vents , Bending (Stress)

Fatigue Monitoring and Related Assessment Method

Advanced Component Fatigue Monitoring Approaches Using the Example of a Boiler Recirculation Pump
J. Rudolph, S. Bergholz, K. Metzger, F. Silber, A. Klenk, T. Müller
PVP 2020; V001T01A034https://doi.org/10.1115/PVP2020-21053
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Topics: Boilers , Fatigue , Pumps
A Method for Measuring Combined Stress of Small Bore Piping Around Weld in Field Using Strain Gauge Holder
Tsunemichi Takahama
PVP 2020; V001T01A035https://doi.org/10.1115/PVP2020-21426
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Topics: Pipes , Strain gages , Stress
Fatigue Assessment of Dented Pipeline Specimens
J. L. F. Freire, V. E. L. Paiva, G. L. G. Gonzáles, R. D. Vieira, J. L. C. Diniz, J. E. Maneschy, A. L. F. S. d’Almeida
PVP 2020; V001T01A036https://doi.org/10.1115/PVP2020-21854
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Topics: Fatigue , Pipelines

Fracture Toughness and Other Small Specimen Mechanical Properties

Ductile Crack Growth Resistance and Rotation Behavior of Miniature C(T) Specimen
Tomoki Shinko, Masato Yamamoto
PVP 2020; V001T01A037https://doi.org/10.1115/PVP2020-21104
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Topics: Ductile fracture , Fracture toughness , Rotation , Steel , Fracture (Materials) , Size effect , Temperature , Deformation , Ductile-brittle transition , Evaluation methods
Fracture Toughness Characterization in the Transition and Ductile Regime of an A508 Type Weld Metal With the Mini-CT Geometry Before and After Irradiation
Marlies Lambrecht, Rachid Chaouadi, Inge Uytdenhouwen, Robert Gérard
PVP 2020; V001T01A038https://doi.org/10.1115/PVP2020-21515
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Topics: Fracture toughness , Geometry , Irradiation (Radiation exposure) , Metals

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
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Topics: Hydrogen , Pressure vessels , Safety , Carbon reinforced plastics , Design , Metals , Alloys , Fatigue analysis , Steel , Autofrettage
Study on the Influence of Crack Growth Behavior on Fatigue Life in Simulated Reactor Coolant Environment of Different Temperature
Tatsuru Misawa, Takanori Kitada, Takao Nakamura
PVP 2020; V001T01A040https://doi.org/10.1115/PVP2020-21172
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Topics: Fatigue life , Fracture (Materials) , Nuclear reactor coolants , Temperature , Pressurized water reactors , Crack propagation , Fatigue testing , High temperature , High pressure (Physics) , Oxygen
Measurement of the Hydrogen Permeability of Various Polymers for High Pressure Hydrogen Storage Vessels and Valves
Jin-Seob Jang, Nak-Kwan Chung
PVP 2020; V001T01A041https://doi.org/10.1115/PVP2020-21210
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Topics: High pressure (Physics) , Hydrogen , Hydrogen storage , Permeability , Polymers , Valves , Vessels
Method and Application of Pipeline Integrity Management Performance Evaluation
Jing Yang, Ming Li, Lei Shi, Xue Li
PVP 2020; V001T01A042https://doi.org/10.1115/PVP2020-21380
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Topics: Performance evaluation , Pipeline integrity management
Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK
Nicholas Underwood, Paul Nevitt, Andrew Howarth, Nicholas Barron
PVP 2020; V001T01A043https://doi.org/10.1115/PVP2020-21790
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Topics: Advanced materials , Boiling , Carbon , Climate change , Construction , Cooling , Cooling systems , Cutting , Cycles , Design
Qualification of a Non-Standard Piping Component for ASME Pressure Piping Applications
Ronald Haupt, Paul Hirschberg, Mark Sindelar, Maher Kassar
PVP 2020; V001T01A044https://doi.org/10.1115/PVP2020-21861
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Topics: Pipes , Pressure pipes , Failure mechanisms , ASME Standards , Compression , Fatigue , Fittings , Mechanical testing , Piping systems , Rupture

High Temperature Codes and Standards

Elimination of BWR Mark I Program Primary Containment Drywell-to-Wetwell Differential Pressure
Raymond M. Pace, Jason Ritzel
PVP 2020; V001T01A045https://doi.org/10.1115/PVP2020-21001
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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
Nayden Matev, Robert A. Ainsworth, Meini Su, Mark Stevens, Alan Jappy
PVP 2020; V001T01A046https://doi.org/10.1115/PVP2020-21211
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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
Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Masashi Miyazaki
PVP 2020; V001T01A047https://doi.org/10.1115/PVP2020-21328
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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
Corrado Delle Site, Emanuele Artenio, Gennaro Sepede, Matteo Chini, Francesco Giacobbe
PVP 2020; V001T01A048https://doi.org/10.1115/PVP2020-21612
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Topics: Boilers , Engineering standards

Improvement of Flaw Characterization Rules for FFS

Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel
Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa
PVP 2020; V001T01A049https://doi.org/10.1115/PVP2020-21441
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Topics: Finite element analysis , Fracture (Materials) , Fracture mechanics , Fracture toughness , Reactor vessels , Steel , Surface cracks , Cladding systems (Building) , Stress , Anisotropy
Assessment of Flaw Interaction Under Combined Tensile and Bending Stresses: Suitability of ASME Code Case N877-1
Pierre Dulieu, Valéry Lacroix, Kunio Hasegawa
PVP 2020; V001T01A050https://doi.org/10.1115/PVP2020-21452
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Topics: ASME Standards , Bending (Stress) , Stress , Fitness-for-service , Membranes , Pressure , Residual stresses , Stress concentration , Welding
Treatment of the Interaction With the Free Surface of the Component for Combined Subsurface Flaws: Technical Basis for Revision of IWA-3300 and Table IWB/IWC-3510-1
Valéry Lacroix, Pierre Dulieu, Kunio Hasegawa, Vratislav Mares
PVP 2020; V001T01A051https://doi.org/10.1115/PVP2020-21455
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Topics: Acceptance criteria , Finite element methods , Fitness-for-service , Fracture mechanics , Geometry , Pressure
A Comparison of Stress Intensity Factor Solutions for Surface Cracked Plates
C. J. Aird
PVP 2020; V001T01A052https://doi.org/10.1115/PVP2020-21456
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Topics: Plates (structures) , Stress , Surface cracks , American Petroleum Institute , Fitness-for-service , Weight (Mass)
Stress Intensity Factor and Crack Opening Area of Circumferentially-Cracked Pipe Under Torsion Moment
Yifan Huang, Xinjian Duan
PVP 2020; V001T01A053https://doi.org/10.1115/PVP2020-21549
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Topics: Fracture (Materials) , Fracture mechanics , Leak-before-break , Pipes , Stress , Torsion
Allowable External Flaws and Acceptance Standards for High Toughness Ductile Pipes Subjected to Bending Moment and Internal Pressure
Kunio Hasegawa, Yinsheng Li, Valery Lacroix, Vratislav Mares
PVP 2020; V001T01A054https://doi.org/10.1115/PVP2020-21672
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Topics: Acceptance criteria , Fracture toughness , Pipes , Pressure , Stress , Failure , ASME Standards
Prediction of Collapse Load Reduction due to Non-Aligned Multiple Flaws
Fuminori Iwamatsu, Katsumasa Miyazaki, Koichi Saito
PVP 2020; V001T01A055https://doi.org/10.1115/PVP2020-21806
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Topics: Collapse , Stress , Fracture (Materials) , Fracture (Process) , Finite element analysis , Fitness-for-service , Ductile fracture , Flat plates , ASME Boiler and Pressure Vessel Code , Boilers

Master Curve Method and Applications

A Code Case Concerning the Effect of Embrittlement on Index Temperature Metrics
Mark Kirk, Marjorie Erickson
PVP 2020; V001T01A056https://doi.org/10.1115/PVP2020-21185
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Topics: Embrittlement , Temperature , Accounting , Fracture toughness , Nuclear power stations , Safety , Uncertainty
Assessment of the Continued Need for Independent Requirements on Transition Temperature and Upper Shelf Charpy Impact Toughness Metrics in Regulations Pertaining to Nuclear Reactor Pressure Vessels
Mark Kirk, Masato Yamamoto, Marjorie Erickson
PVP 2020; V001T01A057https://doi.org/10.1115/PVP2020-21186
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Topics: Fracture toughness , Nuclear reactors , Phase transition temperature , Pressure vessels , Regulations , Steel , Nuclear power stations , Pressure
Methods to Appropriately Account for Uncertainties in Structural Integrity Assessment Models
Marjorie Erickson, Mark Kirk
PVP 2020; V001T01A058https://doi.org/10.1115/PVP2020-21187
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Topics: Uncertainty , Fracture toughness
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
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Topics: Fracture toughness , Irradiation (Radiation exposure)
Effect of Neutron Irradiation on the Mechanical Properties of an A508 Cl.2 Forging Irradiated in a BAMI Capsule
Inge Uytdenhouwen, Rachid Chaouadi
PVP 2020; V001T01A060https://doi.org/10.1115/PVP2020-21513
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Topics: Forging , Fracture toughness , Irradiation (Radiation exposure) , Mechanical properties , Neutrons

Probabilistic and Risk-Informed Methods for Structural Integrity Assessment

Predicting Pipe Rupture Frequencies Using xLPR
David L. Rudland
PVP 2020; V001T01A061https://doi.org/10.1115/PVP2020-21080
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Topics: Fracture mechanics , Pipes , Rupture
Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor
Kai Lu, Jinya Katsuyama, Yinsheng Li
PVP 2020; V001T01A062https://doi.org/10.1115/PVP2020-21421
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Topics: Boiling water reactors , Fracture mechanics , Reactor vessels , Transients (Dynamics) , Fracture (Materials) , Pressurized water reactors , Surface cracks , Computational methods , Embrittlement , Irradiation (Radiation exposure)
Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP
Akihiro Mano, Jinya Katsuyama, Yinsheng Li
PVP 2020; V001T01A063https://doi.org/10.1115/PVP2020-21427
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Topics: Fracture mechanics , Stress corrosion cracking , Water , Stress , Boiling water reactors , Collaboration , Failure , Fatigue , Nuclear power , Nuclear power stations
Improved Bayesian Update Method on Flaw Distributions Reflecting Non-Destructive Inspection Result
Jinya Katsuyama, Yuhei Miyamoto, Kai Lu, Akihiro Mano, Yinsheng Li
PVP 2020; V001T01A064https://doi.org/10.1115/PVP2020-21430
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Topics: Fracture mechanics , Nondestructive evaluation , Reactor vessels
Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels
Hisashi Takamizawa, Yutaka Nishiyama, Takashi Hirano
PVP 2020; V001T01A065https://doi.org/10.1115/PVP2020-21698
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Topics: Brittleness , Embrittlement , Irradiation (Radiation exposure) , Notch testing , Phase transition temperature , Reactor vessels , Statistics , Steel , Uncertainty

Recent Developments in ASME Codes and Standards

Uncertainty Quantification of Viscoplastic Parameters for Grade 91 Steel Through Bayesian Analysis
Aritra Chakraborty, M. C. Messner, T.-L. Sham
PVP 2020; V001T01A066https://doi.org/10.1115/PVP2020-21306
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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
B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham
PVP 2020; V001T01A067https://doi.org/10.1115/PVP2020-21469
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Topics: Design methodology , High temperature , Nuclear reactors , Design , Coolants , Corrosion resistant materials , Corrosion , Creep , Failure , Finite element analysis
A High Temperature Primary Load Design Method Based on Elastic Perfectly-Plastic and Simplified Inelastic Analysis
M. C. Messner, R. I. Jetter, T.-L. Sham
PVP 2020; V001T01A068https://doi.org/10.1115/PVP2020-21470
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Topics: Design methodology , High temperature , Inelastic analysis , Stress , Creep , Design , Damage , Finite element analysis , ASME Boiler and Pressure Vessel Code , Computer software
Investigating the Correlation Between Different Effective Stress Measures and the Service Life of Actual High-Temperature Structural Components
Andrea Rovinelli, Mark C. Messner, T.-L. Sham
PVP 2020; V001T01A069https://doi.org/10.1115/PVP2020-21471
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Topics: High temperature , Service life (Equipment) , Stress , Structural elements (Construction) , Creep , Fracture (Materials) , Fitness-for-service , Rupture , ASME Boiler and Pressure Vessel Code , Damage
Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components
B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham
PVP 2020; V001T01A070https://doi.org/10.1115/PVP2020-21493
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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
B. Barua, M. C. Messner, A. Rovinelli, T.-L. Sham
PVP 2020; V001T01A071https://doi.org/10.1115/PVP2020-21494
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Topics: Acceptance criteria , Base metals , High temperature , Nuclear reactors , Design , Shear stress , Temperature , Design methodology , Bonding , Corrosion resistance
Evaluation of Mean Stress Correction on Fatigue Curves of Grade 91 and Alloy 617 in ASME Section III Division 5
Y. Wang, M. D. McMurtrey, R. I. Jetter, T.-L. Sham
PVP 2020; V001T01A072https://doi.org/10.1115/PVP2020-21572
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Topics: Alloys , Fatigue , Stress , Temperature
The Impact of Geometric Discontinuities on Alloy 617 Creep-Rupture Behavior
Ryann E. Rupp, Michael D. McMurtrey
PVP 2020; V001T01A073https://doi.org/10.1115/PVP2020-21587
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Topics: Alloys , Creep , Rupture , Stress

Recent Developments in Chinese Codes and Standards

Application of Ultrasonic Guided Wave in LMPH Tube of Ethylene Cracking Furnace
Ju Ding, Min Zhang, Shuhong Liu, Minghai Fu, Pugen Zhang, Jielu Wang
PVP 2020; V001T01A074https://doi.org/10.1115/PVP2020-21058
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Topics: Cracking (Materials) , Fracture (Process) , Furnaces , Waves
Inspection Case Analysis of Natural Gas Manifold in a High Acid Gas Field
Jielu Wang, Wenming Song, Xiaoying Tang, Ju Ding, Zhe Pu
PVP 2020; V001T01A075https://doi.org/10.1115/PVP2020-21061
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Topics: Inspection , Manifolds , Natural gas , Natural gas fields
Research on Regulations and Standards for Inspection of Atmospheric Liquid Metal Tank Trucks for Hazardous Chemicals
Zhou Fang, Zhe Wang, Guanghai Li
PVP 2020; V001T01A076https://doi.org/10.1115/PVP2020-21067
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Topics: Inspection , Liquid metals , Regulations , Road transport , Trucks
Study on Acoustic Emission Detection Technology of Fiber Reinforced Plastic Pressure Vessel
Daoxiang Wei, Yuqing Yang, Jun Si, Xiang Wen
PVP 2020; V001T01A077https://doi.org/10.1115/PVP2020-21088
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Topics: Acoustic emissions , Fiber reinforced plastics , Pressure vessels
Research on Implementation Method and Technical Application of Risk Assessment to Storage Tank at National Petroleum Reserves
Zhou Fang, Zhe Wang, Guanghai Li
PVP 2020; V001T01A078https://doi.org/10.1115/PVP2020-21151
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Topics: Crude oil , Inspection , Petroleum , Risk assessment , Storage tanks
Major Hazards Modeling of Pressurized Special Equipment in Chemical Industry Parks Based on FCBPSS Method
Pan Song, Zhe Pu, Bin Ren, Jielu Wang, Shuhong Liu
PVP 2020; V001T01A079https://doi.org/10.1115/PVP2020-21155
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Topics: Chemical industry , Hazards , Modeling
CIVA Simulation and Experiment Verification for Thin-Walled Small-Diameter Pipes by Using Phased Array Ultrasonic Testing
Jun Si, Daoxiang Wei, Yuqing Yang, Xiaoying Tang
PVP 2020; V001T01A080https://doi.org/10.1115/PVP2020-21164
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Topics: Pipes , Simulation , Ultrasonic testing
Analysis of the Flange Seal Groove Cracking in a Hydrocracking Reactor
Fakun Zhuang, Wen Liu, Guoshan Xie, Shanshan Shao, Zhiyuan Han
PVP 2020; V001T01A081https://doi.org/10.1115/PVP2020-21199
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Topics: Flanges , Fracture (Process) , Stress
Study on Numerical Simulation of Gas-Solid Erosion for Horizontal Feed Pipe
Weiwei Hu, Lichen Hu, Li Sun, Chengye Shen, Hu Chen
PVP 2020; V001T01A082https://doi.org/10.1115/PVP2020-21205
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Topics: Computer simulation , Erosion , Pipes , Two-phase flow
A New Method for Preventing Plastic Collapse of Ellipsoidal Head Under Internal Pressure
Keming Li, Jinyang Zheng, Zekun Zhang, Chaohua Gu, Ping Xu
PVP 2020; V001T01A083https://doi.org/10.1115/PVP2020-21212
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Topics: Collapse , Design methodology , Pressure , Pressure vessels
Safety Assessment of Pressure Vessels in Service for More Than 20 Years
Chen Xuedong, Fan Zhichao, Dong Jie, Ai Zhibin, Hu Mingdong
PVP 2020; V001T01A084https://doi.org/10.1115/PVP2020-21238
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Topics: Pressure vessels , Safety
Failure Analysis of Flange Sealing Surface of Outlet Pipeline of Wax Oil Hydrogenation Reactor
Jiqing Shi, Jielu Wang, Wenming Song, Chaopeng Huang
PVP 2020; V001T01A085https://doi.org/10.1115/PVP2020-21251
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Topics: Failure analysis , Flanges , Pipelines , Sealing (Process)
Experimental Investigation on Burst Pressure and Fatigue Life of Type IV LPG Cylinders
Ange Wen, Chuanchuan Shen, Chunyong Hao, Jinyang Zheng
PVP 2020; V001T01A086https://doi.org/10.1115/PVP2020-21264
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Topics: Cylinders , Fatigue life , Pressure , Cycles , Composite materials , Corrosion resistance , Design , Explosions , Fibers , Fire
Fitness for Service Assessment of a Propylene Heat Exchanger Subjected to Fire Damage
Shanshan Shao, Luowei Cao, Guodong Jia, Zhiyuan Han
PVP 2020; V001T01A087https://doi.org/10.1115/PVP2020-21342
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Topics: Damage , Fire , Fitness-for-service , Heat exchangers
Research on Chinese Codes and Standards of Heat Transfer Performance Testing for Heat Exchangers
Bin Ren, Xiaoying Tang, Facai Ren, Jibing Wang, Bofeng Bai
PVP 2020; V001T01A088https://doi.org/10.1115/PVP2020-21352
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Topics: Engineering standards , Heat exchangers , Heat transfer , Testing performance
Current Situation and Prospect of Underground Gas Storage Well
Kun Shi, Zhixiang Duan
PVP 2020; V001T01A089https://doi.org/10.1115/PVP2020-21369
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Topics: Hydrogen , Storage
Performance Tests on Gas Storage Wells With/Without Thread Defects
Zhixiang Duan, Kun Shi
PVP 2020; V001T01A090https://doi.org/10.1115/PVP2020-21370
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Topics: Failure mechanisms , Leakage , Storage , Testing performance , Thread , Wells
Comparative Study on Different National Standards for Local Post Weld Heat Treatment of Pressure Vessels
Fang Ji, Guide Deng, Linlin Duan, Cenfan Liu, Xiaonan Zhao
PVP 2020; V001T01A091https://doi.org/10.1115/PVP2020-21417
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Topics: Engineering standards , Heat treating (Metalworking) , Pressure vessels

Recent Developments in European Codes and Standards

Overview of EASICS Weldment Assessment Route Development Through Inelastic Analysis
S. May, S. Bate, M. Chevalier, D. Dean
PVP 2020; V001T01A092https://doi.org/10.1115/PVP2020-21717
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Topics: Creep , Fatigue , Finite element analysis , Geometry , High temperature , Inelastic analysis , Metalwork , Nuclear design , Plant design , Steel
Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
Peter James, David Coon, Colin Austin, Nicholas Underwood, Marc Chevalier, David Dean
PVP 2020; V001T01A093https://doi.org/10.1115/PVP2020-21720
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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
Marc Chevalier, Peter James, Nicholas Underwood
PVP 2020; V001T01A094https://doi.org/10.1115/PVP2020-21721
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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
Lyndon Lamborn, Zeynab Shirband, Ernest Kwok
PVP 2020; V001T01A095https://doi.org/10.1115/PVP2020-21054
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Topics: Fracture (Materials) , Half-life , Inspection , Pipelines , Safety
Investigation of Relationship Between Microhardness and Charpy Impact Energy for Temper Bead Welding Qualification: Part 2
Boeing Smith, Antonio J. Ramirez, Steven L. McCracken, Stephen Tate
PVP 2020; V001T01A096https://doi.org/10.1115/PVP2020-21300
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Topics: Microhardness , Welding , Heat , Alloy steel , Heat treating (Metalworking) , Maintenance , Nuclear industry , Optimization , Testing
Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking
Stephen Marlette, Steven L. McCraken, Christopher Lohse
PVP 2020; V001T01A097https://doi.org/10.1115/PVP2020-21544
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Topics: Fatigue cracks , Maintenance , Pipes , Stainless steel , Overlays (Materials engineering) , Fatigue , Boiling water reactors , Pressurized water reactors , Stress corrosion cracking , Design
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
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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
Madhumanti Bhattacharyya, Indrajit Charit, Krishnan Raja, Jens Darsell, Saumyadeep Jana
PVP 2020; V001T01A099https://doi.org/10.1115/PVP2020-21716
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Topics: Fracture (Materials) , Friction , Maintenance , Microhardness , Stainless steel , Storage , Welding , Plates (structures) , Base metals , Damage
Example Application of Code Case N-894 Rules for Weld Overlay of Thermal Fatigue Cracking
Christopher Lohse, Richard Bax, Minji Fong, Charles Fourcade, Do Jun Shim
PVP 2020; V001T01A100https://doi.org/10.1115/PVP2020-21760
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Topics: Fatigue cracks , Overlays (Materials engineering) , Fatigue , Filler metals , Maintenance , Boiling water reactors , Compression , Nickel alloys , Pressurized water reactors , Stainless steel

Structural Integrity of Pressure Components

Strain Limits Against Local Fracture of Vessels and Components
Xian-Xing (Lambert) Li, Feng Xi
PVP 2020; V001T01A101https://doi.org/10.1115/PVP2020-21028
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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
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Topics: Creep , Heat recovery steam generators , Pipelines , Stress , Welding , Aeroelasticity , ASTM International , Drilling , Heating , Modeling
Evaluation of Nozzle P-T Limit Curves for Korea Optimized Power Reactor
Hyunchul Lee, Choonsung Yoo, Youngjae Maeng, Sunghoon Yoo
PVP 2020; V001T01A103https://doi.org/10.1115/PVP2020-21358
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Topics: Nozzles
Technical Basis for Proposed Revisions to ASME Section III Code Case N-891 on Maximum Allowable Indentation Depths in HDPE Pipe to Extend Applicability to PENT Ratings Up to 10,000 Hours
Douglas Scarth, Prabhat Krishnaswamy, Phillip Rush, Douglas Munson
PVP 2020; V001T01A104https://doi.org/10.1115/PVP2020-21566
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Topics: Pipes
Local Failure Analysis of Bolted Flanges
Qi Li, Rafal Sulwinski, Charles Boellstorff
PVP 2020; V001T01A105https://doi.org/10.1115/PVP2020-21569
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Topics: Bolted flanges , Damage , Design , Failure , Failure analysis , Stress , ASME Boiler and Pressure Vessel Code , Flanges , Pressure , Tension
Background on Low Temperature Overpressure Protection System Setpoints for Pressure-Temperature Curves
Jeffrey C. Poehler, Gary L. Stevens, Anees A. Udyawar, Amy Freed
PVP 2020; V001T01A106https://doi.org/10.1115/PVP2020-21663
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Topics: Low temperature , Overpressure protection , Pressure , Temperature
Analysis of HDPE Failure Data in Support of Development of Flaw Acceptance Criteria for Butt Fusion Joints
Cheng Liu, Douglas Scarth, Douglas P. Munson, Ryan Wolfe
PVP 2020; V001T01A107https://doi.org/10.1115/PVP2020-21783
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Topics: Acceptance criteria , Failure data , Stress , Pipes , Failure , Temperature , Density , Fracture (Materials) , Inspection , Safety

Total Life Reliability Methods

Application of Environmentally Assisted Fatigue Transient Ramp Times Optimization in Design Evaluations and Fatigue Monitoring Algorithms
Eric Matthews, Mark Gray
PVP 2020; V001T01A108https://doi.org/10.1115/PVP2020-21545
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Topics: Algorithms , Design , Fatigue , Optimization , Transients (Dynamics)
Proposal for a Total Fatigue Life Assessment Methodology That Predicts Fatigue Life From Defect Initiation to Through Wall Leak
Joseph Batten, Chris Currie, Jonathan Mann, Andrew Morley
PVP 2020; V001T01A109https://doi.org/10.1115/PVP2020-21706
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Topics: Fatigue life , Leakage , Fatigue , Design , Fatigue cracks , Modeling , Pipes , Reliability
Probabilistic Leak Before Break Using the R6 Methodology
Peter Gill
PVP 2020; V001T01A110https://doi.org/10.1115/PVP2020-21769
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Topics: Leak-before-break , Stress , Computer software , Failure , Probability , Reliability , Fracture (Materials) , Fracture mechanics , Inspection , Leakage
Fatigue Failure Predictions Based on FEA Fracture Mechanics Simulations
F. H. E. de Haan - de Wilde, M. H. C. Hannink, F. J. Blom
PVP 2020; V001T01A111https://doi.org/10.1115/PVP2020-21846
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Topics: Engineering simulation , Fatigue failure , Fatigue life , Finite element analysis , Fracture (Materials) , Fracture mechanics , Nozzles , Simulation

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
T. Daniel, M. Smaga, T. Beck, T. Schopf, L. Stumpfrock, S. Weihe, J. Rudolph
PVP 2020; V001T01A112https://doi.org/10.1115/PVP2020-21460
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Topics: Fatigue , High cycle fatigue , Stainless steel , Temperature , Welded joints
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