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

Topics: Boilers , Evaluation methods , Fracture (Materials) , Fracture (Process) , Fracture mechanics , Japan Society of Mechanical Engineers , Leak-before-break , Pressure vessels , Sodium fast reactors

Technical Basis for Revision to Code Case N-702

Matthew Walter, Kevin Wong, Nathaniel G. Cofie, Mo Uddin, Gary Dominguez

PVP 2023; V001T01A004https://doi.org/10.1115/PVP2023-107044

Abstract

View Articletitled, Technical Basis for Revision to Code Case N-702

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Topics: Acceptance criteria , ASME Standards , Boiling water reactors , Engineering standards , Failure , Feedwater , Fracture mechanics , In-service inspection , Inspection , Nozzles

Suggested Improvements to ASME Code Section XI, Nonmandatory Appendix L Flaw Tolerance Approach

Alexandria Scott, Anees Udyawar, Joshua Coleman, Nathan Glunt

PVP 2023; V001T01A005https://doi.org/10.1115/PVP2023-107388

Abstract

View Articletitled, Suggested Improvements to ASME Code Section XI, Nonmandatory Appendix L Flaw Tolerance Approach

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Topics: ASME Standards , Fatigue , Fracture (Materials)

Constraint Effects on C&S

Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region (Report 3)

Kiminobu Hojo, Takatoshi Hirota, Yasuto Nagoshi, Takuya Fukahori, Kimihisa Sakima, Mitsuru Ohata, Fumiyoshi Minami

PVP 2023; V001T01A006https://doi.org/10.1115/PVP2023-105965

Abstract

View Articletitled, Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region (Report 3)

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Topics: Ductile fracture , Ductile-brittle transition , Fracture (Materials) , Fracture (Process) , Stress , Temperature

Effect of Postweld Heat Treatment and Temper Bead Welding on the Hydrogen Induced Cracking Susceptibility in the Heat Affected Zone of SA-508 Pressure Vessel Steel

Abbas Mohammadi, Steven L. McCracken, Boian T. Alexandrov

PVP 2023; V001T01A007https://doi.org/10.1115/PVP2023-106079

Abstract

View Articletitled, Effect of Postweld Heat Treatment and Temper Bead Welding on the Hydrogen Induced Cracking Susceptibility in the Heat Affected Zone of SA-508 Pressure Vessel Steel

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Topics: Cracking (Materials) , Fracture (Process) , Heat , Heat treating (Metalworking) , Hydrogen , Pressure vessels , Steel , Welding

Comparison of Impact Toughness Properties in Grade 22 Steel HAZ After PWHT and Temper Bead Welding

Eun Jang, Boian Alexandrov, Steven L. McCracken, Darren Barborak

PVP 2023; V001T01A008https://doi.org/10.1115/PVP2023-106089

Abstract

View Articletitled, Comparison of Impact Toughness Properties in Grade 22 Steel HAZ After PWHT and Temper Bead Welding

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Topics: Fracture toughness , Steel , Welding

Consideration of Geometrical Effect in Fracture Mechanics Assessment for a Vessel Low Alloy Steel

Jules Louerat, Olivier Ancelet, Stephane Marie, Stephane Chapuliot, Anna Dahl

PVP 2023; V001T01A009https://doi.org/10.1115/PVP2023-106100

Abstract

View Articletitled, Consideration of Geometrical Effect in Fracture Mechanics Assessment for a Vessel Low Alloy Steel

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Topics: Alloy steel , Brittleness , Fracture mechanics , Vessels

Application of the J-Q Methodology to Consider the Geometrical Effect on Fracture for Large Steam-Generator Tubesheet

Olivier Ancelet, Stephane Marie, Stéphane Chapuliot, Aurore Parrot

PVP 2023; V001T01A010https://doi.org/10.1115/PVP2023-106269

Abstract

View Articletitled, Application of the J-Q Methodology to Consider the Geometrical Effect on Fracture for Large Steam-Generator Tubesheet

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Topics: Boilers , Brittleness , Fracture (Materials) , Fracture mechanics , Databases , Alloy steel , Alloys , Failure , Geometry , Probability

Developments in HDPE, Buried and Non-Metallic Pipe Codes and Standards

Study on Molten Zone of Butt Fusion Welding Process With Phased Array Ultrasonic Technology for Polyethylene Pipe

Yangji Tao, Weican Guo, Yan Shi, Cunjian Miao, Ping Tang

PVP 2023; V001T01A011https://doi.org/10.1115/PVP2023-106845

Abstract

View Articletitled, Study on Molten Zone of Butt Fusion Welding Process With Phased Array Ultrasonic Technology for Polyethylene Pipe

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Topics: Polyethylene pipes , Welding

Environmental Fatigue Issues (Joint with M&F)

INCEFA-SCALE Project – Overview of the Modelling Plans

Stephan Courtin, Olivier Ancelet, Jack Beswick, Oliver Blakesley, Roman Cicero

PVP 2023; V001T01A012https://doi.org/10.1115/PVP2023-101351

Abstract

View Articletitled, INCEFA-SCALE Project – Overview of the Modelling Plans

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Topics: Data mining , Fatigue , Modeling , Electric arc furnaces , Fatigue damage , Design , Finite element analysis , Nuclear power stations , Numerical analysis , Pressurized water reactors

Technical Revisions of JSME Environmental Fatigue Evaluation Method

Seiji Asada, Takao Nakamura, Masayuki Kamaya, Yukio Takahashi

PVP 2023; V001T01A013https://doi.org/10.1115/PVP2023-102692

Abstract

View Articletitled, Technical Revisions of JSME Environmental Fatigue Evaluation Method

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Topics: Evaluation methods , Fatigue , Japan Society of Mechanical Engineers

Microstructure Characterization of EU INCEFA-SCALE 316L Stainless Steel Fatigue Specimens – Mechanistic Understanding

Aleks Vainionpää, Julio Spadotto, Zaiqing Que, Brian Connolly, Alec Mclennan, Sergio Arrieta, Joseph Huret, Thomas Damiani

PVP 2023; V001T01A014https://doi.org/10.1115/PVP2023-105888

Abstract

View Articletitled, Microstructure Characterization of EU INCEFA-SCALE 316L Stainless Steel Fatigue Specimens – Mechanistic Understanding

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Topics: Electron microscopy , Fatigue , Finishes , Pressurized water reactors , Stainless steel

Influence of Insensitive Strain Region for Strain Rate on Fatigue Life of Stainless Steel in PWR Primary Water Environment

Masayuki Kamaya

PVP 2023; V001T01A015https://doi.org/10.1115/PVP2023-105889

Abstract

View Articletitled, Influence of Insensitive Strain Region for Strain Rate on Fatigue Life of Stainless Steel in PWR Primary Water Environment

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Topics: Fatigue life , Pressurized water reactors , Stainless steel , Water

EPR Piping Material Study: Effects of Sampling Location and Temperature on Low Cycle Fatigue in Air

Tommi Seppänen, Jouni Alhainen, Esko Arilahti, Jussi Solin, Rami Vanninen

PVP 2023; V001T01A016https://doi.org/10.1115/PVP2023-106439

Abstract

View Articletitled, EPR Piping Material Study: Effects of Sampling Location and Temperature on Low Cycle Fatigue in Air

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Topics: Fatigue , Low cycle fatigue , Pipes , Stainless steel , Temperature , Databases , Risk-based inspection

INCEFA-SCALE Project – Data Mining and Lessons Learning

Roman Cicero, Alec McLennan, Jonathan Mann, Jack Beswick, Luc Doremus, Sam Cuvilliez

PVP 2023; V001T01A017https://doi.org/10.1115/PVP2023-106618

Abstract

View Articletitled, INCEFA-SCALE Project – Data Mining and Lessons Learning

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Topics: Data mining , Databases , Fatigue

Shoulder Control for Fatigue Endurance Tests Carried Out Under Variable Amplitude Loading Conditions

James Meldrum, Peter Gill, Jonathan Mann, Alec McLennan, Norman Platts, Michael Toal

PVP 2023; V001T01A018https://doi.org/10.1115/PVP2023-107205

Abstract

View Articletitled, Shoulder Control for Fatigue Endurance Tests Carried Out Under Variable Amplitude Loading Conditions

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Topics: Electric arc furnaces , Fatigue

Fatigue and Fracture Assessment & Management – A Probabilistic Perspective

A Failure-Probability- and Damage-State-Based Fatigue and Creep Model for Estimating Reliability of Stainless Steel 316L(N) Components in Thermal Fatigue

Jeffrey T. Fong, Pedro V. Marcal, Marvin J. Cohn, N. Alan Heckert

PVP 2023; V001T01A019https://doi.org/10.1115/PVP2023-106831

Abstract

View Articletitled, A Failure-Probability- and Damage-State-Based Fatigue and Creep Model for Estimating Reliability of Stainless Steel 316L(N) Components in Thermal Fatigue

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Topics: Creep , Damage , Failure , Fatigue , Inspection , Modeling , Pipes , Power stations , Pressure vessels , Probability

A Multi-Scale Creep, Fatigue, and Creep-Fatigue Interaction Model for Estimating Reliability of Steel Components at Elevated Temperatures

Jeffrey T. Fong, Pedro V. Marcal, Marvin J. Cohn, N. Alan Heckert

PVP 2023; V001T01A020https://doi.org/10.1115/PVP2023-106834

Abstract

View Articletitled, A Multi-Scale Creep, Fatigue, and Creep-Fatigue Interaction Model for Estimating Reliability of Steel Components at Elevated Temperatures

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Topics: Creep , Damage , Failure , Fatigue , Inspection , Modeling , Pipes , Pressure vessels , Probability , Reliability

Fatigue and Ratcheting Issues in Pressure Vessel and Piping Design

A Round Robin Evaluation of Elastic-Plastic Strain Measures for Fatigue Analysis

Cory S. Matusin, Thomas M. Damiani

PVP 2023; V001T01A021https://doi.org/10.1115/PVP2023-101728

Abstract

View Articletitled, A Round Robin Evaluation of Elastic-Plastic Strain Measures for Fatigue Analysis

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Topics: Fatigue , Fatigue analysis , Pipes , Stress , ASME Boiler and Pressure Vessel Code , Pressure vessels , Design , Geometry , Instrumentation , Light water reactors

Assessment of Fatigue Using Elastic-Plastic Analysis in ASME Section III Appendix XIII: A Proposed Approach and Technical Justification

Thomas M. Damiani, Cory S. Matusin

PVP 2023; V001T01A022https://doi.org/10.1115/PVP2023-107430

Abstract

View Articletitled, Assessment of Fatigue Using Elastic-Plastic Analysis in ASME Section III Appendix XIII: A Proposed Approach and Technical Justification

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Topics: Fatigue

Comparative Analysis of Calculation Methods for Fatigue Crack Growth Life of Hydrogen Storage Vessels

Jinhui Wang, Xiaoliang Jia, Fang Ji, Zhiwei Chen, Yunmeng Zhou, Honglian Ma, Kaibo Wang

PVP 2023; V001T01A023https://doi.org/10.1115/PVP2023-107601

Abstract

View Articletitled, Comparative Analysis of Calculation Methods for Fatigue Crack Growth Life of Hydrogen Storage Vessels

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Topics: Computational methods , Fatigue cracks , Hydrogen storage , Vessels

Fatigue Monitoring and Related Assessment Method

Safe Life of Line Pipe in Hydrogen Blended Transport

Duncan Wang, James Hogan, Lyndon Lamborn

PVP 2023; V001T01A024https://doi.org/10.1115/PVP2023-105812

Abstract

View Articletitled, Safe Life of Line Pipe in Hydrogen Blended Transport

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Topics: Fatigue , Hydrogen , Pipes , Stress

Development of a New Thermo-Mechanical Load and Fatigue Monitoring Approach Based on Electromagnetic Acoustic Transducers - EMUS-4-STRESS

Miriam Weikert-Müller, Fabian Weber, Sascha Thieltges, Marek Smaga, Fabian Silber, Jürgen Rudolph, Steffen Bergholz, Eduard Bechtgold

PVP 2023; V001T01A025https://doi.org/10.1115/PVP2023-107274

Abstract

View Articletitled, Development of a New Thermo-Mechanical Load and Fatigue Monitoring Approach Based on Electromagnetic Acoustic Transducers - EMUS-4-STRESS

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Topics: Acoustics , Cycles , Fatigue , Flight , Stress , Temperature , Thermomechanics , Transducers , Transients (Dynamics) , Wall temperature

Fracture Toughness and Other Small Specimen Mechanical Properties (Joint with MF)

Test Temperature Selection Procedures for Small Specimen Master Curve Tests Considering the Possibility of Inhomogeneous Materials

Masato Yamamoto, Mark Kirk

PVP 2023; V001T01A026https://doi.org/10.1115/PVP2023-101326

Abstract

View Articletitled, Test Temperature Selection Procedures for Small Specimen Master Curve Tests Considering the Possibility of Inhomogeneous Materials

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Topics: Fracture toughness , Temperature , ASTM International , Deformation , Reactor vessels , Steel , Weibull distribution , Yield stress

Analysis of the Effect of Pre-Crack Curvature in Mini-C(T) Specimen on Fracture Toughness Evaluation

Masaki Shimodaira, Yoosung Ha, Hisashi Takamizawa, Jinya Katsuyama, Kunio Onizawa

PVP 2023; V001T01A027https://doi.org/10.1115/PVP2023-102699

Abstract

View Articletitled, Analysis of the Effect of Pre-Crack Curvature in Mini-C(T) Specimen on Fracture Toughness Evaluation

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Topics: Finite element analysis , Fracture (Materials) , Fracture toughness

Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening

Aniruddh Das, Paul Chekhonin, Mario Houska, Florian Obermeier, Eberhard Altstadt

PVP 2023; V001T01A028https://doi.org/10.1115/PVP2023-103648

Abstract

View Articletitled, Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening

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Topics: Fractography , Hardening , Neutrons , Steel , Temperature , Fracture (Materials) , Irradiation (Radiation exposure) , Embrittlement , Fracture toughness , Yield strength

Fracture Characterization of Structural Steel S275JR Using Conventional CT Specimens, Mini-CT Specimens and Small Punch Specimens: A Comparison

Marcos Sánchez, Sergio Cicero, Borja Arroyo

PVP 2023; V001T01A029https://doi.org/10.1115/PVP2023-105437

Abstract

View Articletitled, Fracture Characterization of Structural Steel S275JR Using Conventional CT Specimens, Mini-CT Specimens and Small Punch Specimens: A Comparison

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Topics: Fracture (Materials) , Fracture (Process) , Structural steel , Temperature

Present Status of the Fractesus Project: Round Robin on Unirradiated Materials

G. Bonny, E. Altstadt, P. Arffman, S. Cicero, F. Obermeier, T. Petit, H. Swan, R. Chaouadi, E. Gaganidze, B. Hargitai, M. Kolluri, R. Kopriva, P. Rozsahegyi, M. Serrano, P. Spätig, I. Uytdenhouwen, H. Wilcox, M. Yamamoto

PVP 2023; V001T01A030https://doi.org/10.1115/PVP2023-105449

Abstract

View Articletitled, Present Status of the Fractesus Project: Round Robin on Unirradiated Materials

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Topics: Computer software , Displacement , Fracture toughness , Reactor vessels , Stress , Temperature , Tension , Testing , Welded joints

Linkage of Fracture Assessment Methodology With Fracture Toughness Testing Procedures

Adam J. Cooper, Peter James, John Sharples

PVP 2023; V001T01A031https://doi.org/10.1115/PVP2023-105571

Abstract

View Articletitled, Linkage of Fracture Assessment Methodology With Fracture Toughness Testing Procedures

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Topics: Fracture (Materials) , Fracture toughness , Linkages , Testing , ASTM International , Plasticity , Fracture mechanics , Structural elements (Construction) , Failure , Structural steel

Literature Review on Testing of Mini-CT Specimen to Characterize the Ductile-to-Brittle Transition Range and the Upper Shelf Regime

Marcos Sánchez, Sergio Cicero, Sergio Arrieta

PVP 2023; V001T01A032https://doi.org/10.1115/PVP2023-105596

Abstract

View Articletitled, Literature Review on Testing of Mini-CT Specimen to Characterize the Ductile-to-Brittle Transition Range and the Upper Shelf Regime

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Topics: Brittleness , Testing , Steel , Geometry , Displacement , Fracture (Materials) , Fracture (Process) , Fracture toughness , Reactor vessels , Stress

Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management

Mark Kirk, Marjorie Erickson, Elliot J. Long

PVP 2023; V001T01A033https://doi.org/10.1115/PVP2023-105904

Abstract

View Articletitled, Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management

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Topics: ASME Standards , Base metals , Electromagnetic scattering , Embrittlement , Fracture toughness , Heat , Irradiation (Radiation exposure) , Metals , Neutrons , Phase transition temperature

Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens

Timo Metzler, Ermile Gaganidze, Jarir Aktaa

PVP 2023; V001T01A034https://doi.org/10.1115/PVP2023-105918

Abstract

View Articletitled, Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens

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Topics: Fracture toughness , Reactor vessels , Steel

The Effect of Loss of Constraint on the Initiation of Ductile Fracture in a Mini-CT

Meng Li, Rachid Chaouadi, Inge Uytdenhouwen, Thomas Pardoen, Giovanni Bonny

PVP 2023; V001T01A035https://doi.org/10.1115/PVP2023-106216

Abstract

View Articletitled, The Effect of Loss of Constraint on the Initiation of Ductile Fracture in a Mini-CT

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Topics: Ductile fracture , Finite element analysis , Micromechanics (Engineering) , Simulation

Sub-Sized Creep Specimen Testing for High Throughput and Post-Irradiation Testing

Michael D. McMurtrey, Ninad Mohale

PVP 2023; V001T01A036https://doi.org/10.1115/PVP2023-107524

Abstract

View Articletitled, Sub-Sized Creep Specimen Testing for High Throughput and Post-Irradiation Testing

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Topics: Alloys , Creep , Irradiation (Radiation exposure) , Testing

High Temperature Codes and Standards

Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Satoshi Okajima

PVP 2023; V001T01A037https://doi.org/10.1115/PVP2023-105707

Abstract

View Articletitled, Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading

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Topics: Buckling , Evaluation methods , Fast neutron reactors , Stainless steel , Steel , Testing , Vessels , Stress , Design , Yield stress

Development of a Web-Based Design Evaluation Platform for Elevated Temperature Design as per ASME Section III Division 5, ASME CC-2843 and RCC-MRx

Hyeong-Yeon Lee, Ki-Ean Nam, Nam-Su Huh, Min-Kyu Kim

PVP 2023; V001T01A038https://doi.org/10.1115/PVP2023-106584

Abstract

View Articletitled, Development of a Web-Based Design Evaluation Platform for Elevated Temperature Design as per ASME Section III Division 5, ASME CC-2843 and RCC-MRx

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Topics: Creep , Design , Generation IV reactors , Temperature

Analysis of Piping Components for High Temperature-Example Problem

Reza Adibi-Asl

PVP 2023; V001T01A039https://doi.org/10.1115/PVP2023-107112

Abstract

View Articletitled, Analysis of Piping Components for High Temperature-Example Problem

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Topics: High temperature , Pipes , Temperature

Hydrogen Effects on Material Behavior for Structural Integrity Assessment (Joint with MF)

Technical Basis of ASME B31.12 Code Case 218: Use of Enhanced Materials Performance Factors (H_f and M_f) of 1.0

Kang Xu, Mahendra Rana

PVP 2023; V001T01A040https://doi.org/10.1115/PVP2023-105727

Abstract

View Articletitled, Technical Basis of ASME B31.12 Code Case 218: Use of Enhanced Materials Performance Factors (Hf and Mf) of 1.0

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Topics: Construction , Design , Engineering standards , Fracture mechanics , Heat treating (Metalworking) , High pressure (Physics) , Hydrogen , Hydrogen embrittlement , Manufacturing , Materials degradation

Comparison of Design Approaches on the Design Lifetime Prediction of Gaseous Hydrogen Storage Tanks

Carl Fischer, Heiner Oesterlin, Thorsten Michler

PVP 2023; V001T01A041https://doi.org/10.1115/PVP2023-105732

Abstract

View Articletitled, Comparison of Design Approaches on the Design Lifetime Prediction of Gaseous Hydrogen Storage Tanks

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Topics: Design , Hydrogen , Hydrogen storage , Stress

Comparison of the Fatigue Life in Hydrogen Environment Using ASME Section VIII, Division 3 and ASME Section VIII, Division 2

Koray Kuscu, Mandeep Singh

PVP 2023; V001T01A042https://doi.org/10.1115/PVP2023-107120

Abstract

View Articletitled, Comparison of the Fatigue Life in Hydrogen Environment Using ASME Section VIII, Division 3 and ASME Section VIII, Division 2

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Topics: Fatigue life , Hydrogen , Hydrogen embrittlement , Fracture (Materials) , Fatigue , American Petroleum Institute , Carbon , Emissions , Failure mechanisms , Fitness-for-service

Improvement of Flaw Characterization Rules for FFS

Towards an Improvement of Allowable Planar Flaws of ASME Code Section XI Acceptance Standards for Ferritic Steel Materials

Valéry Lacroix, Pierre Dulieu, Kunio Hasegawa

PVP 2023; V001T01A043https://doi.org/10.1115/PVP2023-103446

Abstract

View Articletitled, Towards an Improvement of Allowable Planar Flaws of ASME Code Section XI Acceptance Standards for Ferritic Steel Materials

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Topics: Acceptance criteria , ASME Standards , Steel , Flaw detection , Fracture toughness , In-service inspection

Revision of Allowable Planar Flaw Tables of ASME B&PV Code Section XI for Ferritic Steel Materials

Pierre Dulieu, Valéry Lacroix, Kunio Hasegawa

PVP 2023; V001T01A044https://doi.org/10.1115/PVP2023-103472

Abstract

View Articletitled, Revision of Allowable Planar Flaw Tables of ASME B&PV Code Section XI for Ferritic Steel Materials

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Topics: Acceptance criteria , ASME Standards , Brittleness , Collapse , Failure , Failure mechanisms , In-service inspection , Safety , Steel , Stress

Master Curve Method and Applications

Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project

Frideriki Naziris, Rebeca Hernandez Pascual, Timo Metzler, Ermile Gaganidze, Inge Uytdenhouwen, Murthy Kolluri

PVP 2023; V001T01A045https://doi.org/10.1115/PVP2023-107254

Abstract

View Articletitled, Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project

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Topics: ASTM International , Design , Embrittlement , Fluence (Radiation measurement) , Fracture toughness , Geometry , Machinery , Machining , Manipulators , Reactor vessels

Mechanical Properties of Nuclear Graphite and Their Implementation in Codes and Standards (Joint with MF)

Simplified Method for Adjusting the Shape and Characteristic Strength Parameters of the Weibull Strength Distribution of Graphite Materials

Michael Saitta, Gwennaël Beirnaert

PVP 2023; V001T01A046https://doi.org/10.1115/PVP2023-105207

Abstract

View Articletitled, Simplified Method for Adjusting the Shape and Characteristic Strength Parameters of the Weibull Strength Distribution of Graphite Materials

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Topics: Graphite , Shapes , Weibull distribution , Algebra , ASME Boiler and Pressure Vessel Code , Maximum likelihood estimation , Nonmetallic materials , Optimization , Probability , Stress analysis (Engineering)

Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite

Steve Johns, William E. Windes

PVP 2023; V001T01A047https://doi.org/10.1115/PVP2023-105209

Abstract

View Articletitled, Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite

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Topics: Graphite , Irradiation (Radiation exposure) , Modeling , Temperature , Molten salt reactors , Nuclear reactors , Atoms , Carbon , Design , Nonmetallic materials

Probabilistic Assessment Tool for Graphite Component Reliability

Joseph Bass, Raj Iyengar, Christopher Ulmer

PVP 2023; V001T01A048https://doi.org/10.1115/PVP2023-106469

Abstract

View Articletitled, Probabilistic Assessment Tool for Graphite Component Reliability

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Topics: Graphite , Modeling , Reliability

Development of a Graphite Irradiation Qualification Plan for the XE-100 Reactor

Anne A. Campbell, Josina W. Geringer, Adrian M. Schrell, Samuel Baylis, Timothy Lucas, Peter J. Pappano, Martin van Staden

PVP 2023; V001T01A049https://doi.org/10.1115/PVP2023-106610

Abstract

View Articletitled, Development of a Graphite Irradiation Qualification Plan for the XE-100 Reactor

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Topics: Graphite , Irradiation (Radiation exposure)

Finite Element Model Mesh Refinement Effects on Qualification of Nuclear Grade Graphite Components

Andrea Mack, William Hoffman, Joseph Bass, William Windes

PVP 2023; V001T01A050https://doi.org/10.1115/PVP2023-107369

Abstract

View Articletitled, Finite Element Model Mesh Refinement Effects on Qualification of Nuclear Grade Graphite Components

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Topics: Finite element analysis , Finite element model , Graphite , Probability , Stress

Probabilistic and Risk-Informed Methods for Structural Integrity Assessment (Joint with MF)

Statistical Approach to Developing a Performance Monitoring Program

David L. Rudland, Dan Widrevitz

PVP 2023; V001T01A051https://doi.org/10.1115/PVP2023-105203

Abstract

View Articletitled, Statistical Approach to Developing a Performance Monitoring Program

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Topics: In-service inspection , Inspection , Light water reactors , Nuclear reactors , Risk , Safety , Service life (Equipment)

Technical Basis for Inspection Optimization and Deferral of PWR Steam Generator Component Examinations

Nathaniel G. Cofie, Dilip Dedhia, Scott T. Chesworth, Do Jun Shim, Robert Grizzi

PVP 2023; V001T01A052https://doi.org/10.1115/PVP2023-105958

Abstract

View Articletitled, Technical Basis for Inspection Optimization and Deferral of PWR Steam Generator Component Examinations

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Topics: Boilers , Inspection , Optimization , Pressurized water reactors , ASME Standards , Pressure , Welded joints , Nozzles , Pressure vessels , Vessels

Probabilistic Fracture Mechanics Evaluation of PWR Cast Austenitic Stainless Steel Piping Components – Axial Cracking Methods and Results

Kevin Fuhr, Matt Wolfson, Glenn White, Markus Burkardt, Do Jun Shim

PVP 2023; V001T01A053https://doi.org/10.1115/PVP2023-107363

Abstract

View Articletitled, Probabilistic Fracture Mechanics Evaluation of PWR Cast Austenitic Stainless Steel Piping Components – Axial Cracking Methods and Results

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Topics: Cracking (Materials) , Fracture (Process) , Fracture mechanics , Pipes , Pressurized water reactors , Stainless steel

A Review of Current Best Practice for Validation of Probabilistic Fracture Mechanics Codes for Assessment of Nuclear Structural Integrity

Steven X. Xu, David L. Rudland, Douglas A. Scarth

PVP 2023; V001T01A054https://doi.org/10.1115/PVP2023-107513

Abstract

View Articletitled, A Review of Current Best Practice for Validation of Probabilistic Fracture Mechanics Codes for Assessment of Nuclear Structural Integrity

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Topics: Fracture mechanics

Recent Developments in ASME Codes and Standards

Development of a Piping Qualification Methodology and Testing – Proposal Enhancement to ASME BPVC and B31 Certification

Irawan Josodipuro

PVP 2023; V001T01A055https://doi.org/10.1115/PVP2023-103837

Abstract

View Articletitled, Development of a Piping Qualification Methodology and Testing – Proposal Enhancement to ASME BPVC and B31 Certification

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Topics: ASME Boiler and Pressure Vessel Code , Pipes , Safety , Testing

A Universal Inelastic Constitutive Model for High Temperature Deformation

Tianju Chen, Mark C. Messner

PVP 2023; V001T01A056https://doi.org/10.1115/PVP2023-105946

Abstract

View Articletitled, A Universal Inelastic Constitutive Model for High Temperature Deformation

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Topics: Constitutive equations , Deformation , High temperature , Design , ASME Standards , Inelastic analysis , Alloys , Nickel , Boilers , Computers

Notch Effect on Creep-Fatigue Behavior of Alloy 617 at Elevated Temperature

Peijun Hou, Yanli Wang, Ting-Leung Sham

PVP 2023; V001T01A057https://doi.org/10.1115/PVP2023-106503

Abstract

View Articletitled, Notch Effect on Creep-Fatigue Behavior of Alloy 617 at Elevated Temperature

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Topics: Alloys , Creep , Fatigue , High temperature , Stress , Temperature

A Method for Evaluation of Creep-Fatigue Life at Low Strain Ranges

Peijun Hou, Yanli Wang, Ting-Leung Sham

PVP 2023; V001T01A058https://doi.org/10.1115/PVP2023-106512

Abstract

View Articletitled, A Method for Evaluation of Creep-Fatigue Life at Low Strain Ranges

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Topics: Alloys , Creep , Fatigue

Path Forward: Materials Data Modernization for ASME Codes and Standards in the Artificial Intelligence Era

Weiju Ren

PVP 2023; V001T01A059https://doi.org/10.1115/PVP2023-106799

Abstract

View Articletitled, Path Forward: Materials Data Modernization for ASME Codes and Standards in the Artificial Intelligence Era

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Topics: Artificial intelligence , ASME Standards , Databases , Engineering standards , Materials properties , Machinery , Waves

Case Study on the Acceptance of a Unique Refractory Material in ASME Section VIII

Daniel T. Peters, Rahul Kapadia, Maarten Hoeijmakers, Harald Koestenbauer, Florian Niggl

PVP 2023; V001T01A060https://doi.org/10.1115/PVP2023-106904

Abstract

View Articletitled, Case Study on the Acceptance of a Unique Refractory Material in ASME Section VIII

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Topics: ASME Standards , ASTM International , Construction , Design , Fatigue analysis , Furnaces , Heating , Hot isostatic presses , Inspection , Metals

A Comprehensive Sample Problem for Section III Division 5 Design by Elastic Analysis

Bipul Barua, M. C. Messner

PVP 2023; V001T01A061https://doi.org/10.1115/PVP2023-107325

Abstract

View Articletitled, A Comprehensive Sample Problem for Section III Division 5 Design by Elastic Analysis

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Topics: Design , Elastic analysis , Pressure vessels , Nozzles , Boilers , Breeder reactors , Carbon , Computer software , Finite element analysis , Heat

Recent Developments in Chinese Codes and Standards

Exploration of Design, Manufacture and Maintenance of Pressure Vessels in China Under Background of the Internet

Xuedong Chen, Zhichao Fan, Shuangqing Xu, Jiushao Hu, Jianxin Zhu

PVP 2023; V001T01A062https://doi.org/10.1115/PVP2023-106217

Abstract

View Articletitled, Exploration of Design, Manufacture and Maintenance of Pressure Vessels in China Under Background of the Internet

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Topics: China , Design , Internet , Maintenance , Pressure vessels , Safety

Research on China’s LNG Terminal Standard System and Intelligent Management Mode

Hangjian Hu, Yongli He, Xin Liu, Zhixiang Duan

PVP 2023; V001T01A063https://doi.org/10.1115/PVP2023-106537

Abstract

View Articletitled, Research on China’s LNG Terminal Standard System and Intelligent Management Mode

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Topics: Liquefied natural gas

Research on Optimization of Database Security System of Chemical Industry Park Structures

Yuxuan Cao, Kejing Liu, Rui Xue, Kaijian Xu, Zhou Fang

PVP 2023; V001T01A064https://doi.org/10.1115/PVP2023-107094

Abstract

View Articletitled, Research on Optimization of Database Security System of Chemical Industry Park Structures

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Topics: Chemical industry , Databases , Optimization , Safety , Security

Study on the Mechanical Response of Gas Cylinders Under Shock Load

Zhou Fang, Gang Wu, Ce Song, Jun Yuan, Zhe Wang

PVP 2023; V001T01A065https://doi.org/10.1115/PVP2023-107108

Abstract

View Articletitled, Study on the Mechanical Response of Gas Cylinders Under Shock Load

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Topics: Finite element analysis , Gas cylinders , Shock (Mechanics) , Stress

Study on Regular Inspection Standard of Large Volume Carbon Fiber Fully Wound Cylinder Bundles

Zhou Fang, Qia Liu, Zhe Wang

PVP 2023; V001T01A066https://doi.org/10.1115/PVP2023-107121

Abstract

View Articletitled, Study on Regular Inspection Standard of Large Volume Carbon Fiber Fully Wound Cylinder Bundles

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Topics: Carbon fibers , Cylinders , High pressure (Physics) , Inspection

Longitudinal Cracking Failure at the Skirt-to-Cone Joint of Large Coke Drum in Delayed Coking Unit

Xin Ma, Yining Wang, Xiaoliang Wang, Yi Xie

PVP 2023; V001T01A067https://doi.org/10.1115/PVP2023-107535

Abstract

View Articletitled, Longitudinal Cracking Failure at the Skirt-to-Cone Joint of Large Coke Drum in Delayed Coking Unit

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Topics: Coke , Cracking (Materials) , Failure , Fracture (Process) , Maintenance

Experimental Investigation on the Pull-Out Strength of Flexibly Expanded Tube-to-Tubesheet Joints

Xin Ma, Wenli Dong, Xiaoliang Wang, Zhiqiang Ge

PVP 2023; V001T01A068https://doi.org/10.1115/PVP2023-107583

Abstract

View Articletitled, Experimental Investigation on the Pull-Out Strength of Flexibly Expanded Tube-to-Tubesheet Joints

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Topics: Carbon steel , China , Construction , Heat exchangers , Pipes , Pressure , Rubber , Shells , Stainless steel

Identification of Typical Damage Mechanism of Coke Drum in Delayed Coking Unit

Xin Ma, Yi Xie, Zhiqiang Ge

PVP 2023; V001T01A069https://doi.org/10.1115/PVP2023-107648

Abstract

View Articletitled, Identification of Typical Damage Mechanism of Coke Drum in Delayed Coking Unit

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Topics: Coke , Damage , Inspection

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

History and Technical Scope of Code Case N-513

Stephen M. Parker, Stephen L. McCracken, Robert O. McGill, Ioannis D. Patten

PVP 2023; V001T01A070https://doi.org/10.1115/PVP2023-106137

Abstract

View Articletitled, History and Technical Scope of Code Case N-513

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Topics: ASME Standards , Carbon steel , Corrosion , Gates (Closures) , Knowledge transfer , Maintenance , Nuclear industry , Pipes , Public utilities , Safety

Elimination of the 48-Hour Hold for Ambient Temperature Temper Bead Welding With Austenitic Weld Metal

Steven L. McCracken, Asif Patel

PVP 2023; V001T01A071https://doi.org/10.1115/PVP2023-107489

Abstract

View Articletitled, Elimination of the 48-Hour Hold for Ambient Temperature Temper Bead Welding With Austenitic Weld Metal

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Topics: Metals , Temperature , Welding , Hydrogen , Nondestructive evaluation , Cracking (Materials) , Fracture (Process) , Gas tungsten arc welding , Machinery , Welded joints