Volumes | Pressure Vessels and Piping Conference | American Society of Mechanical Engineers Digital Collection

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; V001T01A008doi:https://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; V001T01A009doi:https://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; V001T01A010doi:https://doi.org/10.1115/PVP2020-21106

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Topics: Fatigue , Finishes , Pressurized water reactors

Grade and Temperature Dependent Reference Curves for Realistic F_en Quantification of Austenitic Stainless Steels

Tommi Seppänen, Jouni Alhainen, Esko Arilahti, Jussi Solin

PVP 2020; V001T01A011doi:https://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; V001T01A012doi:https://doi.org/10.1115/PVP2020-21220

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Topics: Fatigue , Nuclear power stations , Safety

Further Evidence of Margin for Environmental Effects, Termed F_en-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; V001T01A013doi:https://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; V001T01A014doi:https://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; V001T01A015doi:https://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; V001T01A016doi:https://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; V001T01A017doi:https://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; V001T01A018doi:https://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; V001T01A019doi:https://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; V001T01A020doi:https://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; V001T01A021doi:https://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; V001T01A022doi:https://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; V001T01A023doi:https://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; V001T01A024doi:https://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; V001T01A025doi:https://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; V001T01A026doi:https://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; V001T01A027doi:https://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; V001T01A028doi:https://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; V001T01A029doi:https://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; V001T01A030doi:https://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; V001T01A031doi:https://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; V001T01A032doi:https://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; V001T01A033doi:https://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; V001T01A034doi:https://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; V001T01A035doi:https://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; V001T01A036doi:https://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; V001T01A037doi:https://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; V001T01A038doi:https://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; V001T01A039doi:https://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; V001T01A040doi:https://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; V001T01A041doi:https://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; V001T01A042doi:https://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; V001T01A043doi:https://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; V001T01A044doi:https://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; V001T01A045doi:https://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; V001T01A046doi:https://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; V001T01A047doi:https://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; V001T01A048doi:https://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; V001T01A049doi:https://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; V001T01A050doi:https://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; V001T01A051doi:https://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; V001T01A052doi:https://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; V001T01A053doi:https://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; V001T01A054doi:https://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; V001T01A055doi:https://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; V001T01A056doi:https://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; V001T01A057doi:https://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; V001T01A058doi:https://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; V001T01A059doi:https://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; V001T01A060doi:https://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; V001T01A061doi:https://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; V001T01A062doi:https://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; V001T01A063doi:https://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; V001T01A064doi:https://doi.org/10.1115/PVP2020-21430

Abstract

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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; V001T01A065doi:https://doi.org/10.1115/PVP2020-21698

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Topics: Brittleness , Embrittlement , Irradiation (Radiation exposure) , Notch testing , Phase transition temperature , Reactor vessels , Statistics as topic , 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; V001T01A066doi:https://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; V001T01A067doi:https://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; V001T01A068doi:https://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; V001T01A069doi:https://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; V001T01A070doi:https://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; V001T01A071doi:https://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; V001T01A072doi:https://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; V001T01A073doi:https://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; V001T01A074doi:https://doi.org/10.1115/PVP2020-21058

Abstract

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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; V001T01A075doi:https://doi.org/10.1115/PVP2020-21061

Abstract

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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; V001T01A076doi:https://doi.org/10.1115/PVP2020-21067

Abstract

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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; V001T01A077doi:https://doi.org/10.1115/PVP2020-21088

Abstract

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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; V001T01A078doi:https://doi.org/10.1115/PVP2020-21151

Abstract

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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; V001T01A079doi:https://doi.org/10.1115/PVP2020-21155

Abstract

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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; V001T01A080doi:https://doi.org/10.1115/PVP2020-21164

Abstract

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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; V001T01A081doi:https://doi.org/10.1115/PVP2020-21199

Abstract

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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; V001T01A082doi:https://doi.org/10.1115/PVP2020-21205

Abstract

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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; V001T01A083doi:https://doi.org/10.1115/PVP2020-21212

Abstract

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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; V001T01A084doi:https://doi.org/10.1115/PVP2020-21238

Abstract

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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; V001T01A085doi:https://doi.org/10.1115/PVP2020-21251

Abstract

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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; V001T01A086doi:https://doi.org/10.1115/PVP2020-21264

Abstract

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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; V001T01A087doi:https://doi.org/10.1115/PVP2020-21342

Abstract

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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; V001T01A088doi:https://doi.org/10.1115/PVP2020-21352

Abstract

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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; V001T01A089doi:https://doi.org/10.1115/PVP2020-21369

Abstract

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Topics: Hydrogen , Storage

Performance Tests on Gas Storage Wells With/Without Thread Defects

Zhixiang Duan, Kun Shi

PVP 2020; V001T01A090doi:https://doi.org/10.1115/PVP2020-21370

Abstract

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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; V001T01A091doi:https://doi.org/10.1115/PVP2020-21417

Abstract

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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; V001T01A092doi:https://doi.org/10.1115/PVP2020-21717

Abstract

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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; V001T01A093doi:https://doi.org/10.1115/PVP2020-21720

Abstract

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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; V001T01A094doi:https://doi.org/10.1115/PVP2020-21721

Abstract

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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; V001T01A095doi:https://doi.org/10.1115/PVP2020-21054

Abstract

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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; V001T01A096doi:https://doi.org/10.1115/PVP2020-21300

Abstract

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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; V001T01A097doi:https://doi.org/10.1115/PVP2020-21544

Abstract

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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; V001T01A098doi:https://doi.org/10.1115/PVP2020-21708

Abstract

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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; V001T01A099doi:https://doi.org/10.1115/PVP2020-21716

Abstract

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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; V001T01A100doi:https://doi.org/10.1115/PVP2020-21760

Abstract

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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; V001T01A101doi:https://doi.org/10.1115/PVP2020-21028

Abstract

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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; V001T01A102doi:https://doi.org/10.1115/PVP2020-21077

Abstract

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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; V001T01A103doi:https://doi.org/10.1115/PVP2020-21358

Abstract

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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; V001T01A104doi:https://doi.org/10.1115/PVP2020-21566

Abstract

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Topics: Pipes

Local Failure Analysis of Bolted Flanges

Qi Li, Rafal Sulwinski, Charles Boellstorff

PVP 2020; V001T01A105doi:https://doi.org/10.1115/PVP2020-21569

Abstract

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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; V001T01A106doi:https://doi.org/10.1115/PVP2020-21663

Abstract

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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; V001T01A107doi:https://doi.org/10.1115/PVP2020-21783

Abstract

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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; V001T01A108doi:https://doi.org/10.1115/PVP2020-21545

Abstract

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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; V001T01A109doi:https://doi.org/10.1115/PVP2020-21706

Abstract

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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; V001T01A110doi:https://doi.org/10.1115/PVP2020-21769

Abstract

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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; V001T01A111doi:https://doi.org/10.1115/PVP2020-21846

Abstract

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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; V001T01A112doi:https://doi.org/10.1115/PVP2020-21460

Abstract

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Topics: Fatigue , High cycle fatigue , Stainless steel , Temperature , Welded joints

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Proceedings Papers

Codes and Standards

ASME Code Section XI Activities

Environmental Fatigue Issues (Joint M&F)

Fatigue and Fracture Assessment and Management: A Probabilistic Perspective

Fatigue and Ratcheting Issues in Pressure Vessel and Piping Design

Fatigue Monitoring and Related Assessment Method

Fracture Toughness and Other Small Specimen Mechanical Properties

General Codes and Standards for Pressure Equipment Overview

High Temperature Codes and Standards

Improvement of Flaw Characterization Rules for FFS

Master Curve Method and Applications

Probabilistic and Risk-Informed Methods for Structural Integrity Assessment

Recent Developments in ASME Codes and Standards

Recent Developments in Chinese Codes and Standards

Recent Developments in European Codes and Standards

Repair, Replacement, and Mitigation for Fitness-for-Service Rules

Structural Integrity of Pressure Components

Total Life Reliability Methods

Very High Cycle Fatigue Behavior

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