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ASME 2010 Pressure Vessels and Piping Conference: Volume 1

Codes and Standards

API 579/ASME Code Fitness-for-Service Activities

Discussion on Plastic Collapse Criterion at High Temperatures in FFS Assessment Rules

Kenji Oyamada, Shinji Konosu, Hikaru Miyata, Takashi Ohno

PVP 2010; 3-13https://doi.org/10.1115/PVP2010-25500

Abstract

View Articletitled, Discussion on Plastic Collapse Criterion at High Temperatures in FFS Assessment Rules

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Topics: Collapse , Fitness-for-service , High temperature , Metals , American Petroleum Institute , Earthquakes , Finite element analysis , High temperature materials , Pipes , Pressure

Development of Fragility Curve Considering Aging of Oil Storage Tanks and Its Application to Risk Assessment of Industrial Complexes

Yoshihisa Murakami, Toshiro Yamase, Shinsaku Zama, Yoshihiro Hirokawa, Haruki Nishi, Minoru Yamada, Akiko Hirano, Naoya Kasai

PVP 2010; 15-18https://doi.org/10.1115/PVP2010-25508

Abstract

View Articletitled, Development of Fragility Curve Considering Aging of Oil Storage Tanks and Its Application to Risk Assessment of Industrial Complexes

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Topics: Risk assessment , Storage tanks , Shells , Buckling , Disasters , Earthquakes , Emergency management , Fire , Construction , Corrosion

Research and Development of a Double Steel Bottom Structure of Oil Storage Tank

Zhiping Chen, Liuchuan Yan, Zhou Fang, Guowei Cao

PVP 2010; 19-25https://doi.org/10.1115/PVP2010-25537

Abstract

View Articletitled, Research and Development of a Double Steel Bottom Structure of Oil Storage Tank

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Topics: Industrial research , Leakage , Steel , Storage tanks

Comparison of Thermo-Mechanical Fatigue Life Assessment Methods for Coke Drums

Jorge A. Penso, Radwan Hazime

PVP 2010; 27-35https://doi.org/10.1115/PVP2010-25810

Abstract

View Articletitled, Comparison of Thermo-Mechanical Fatigue Life Assessment Methods for Coke Drums

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Topics: Coke , Fatigue life , Thermomechanics , Stress , Fatigue , Fracture (Materials) , Finite element analysis , Stress analysis (Engineering) , Cracking (Materials) , Fracture (Process)

ASME Code Section XI Activities

Technical Basis for a Flaw Tolerance Option for Code Case N-770-1 for Large Diameter Cold Leg Piping to Main Coolant Pump Welds, With Obstructions

Warren Bamford, Reddy Ganta, Gordon Hall, Matthew Kelley

PVP 2010; 39-49https://doi.org/10.1115/PVP2010-25145

Abstract

View Articletitled, Technical Basis for a Flaw Tolerance Option for Code Case N-770-1 for Large Diameter Cold Leg Piping to Main Coolant Pump Welds, With Obstructions

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Topics: Coolants , Pipes , Pumps , Welded joints , Inspection , Nozzles , Alloys , ASME Standards , Defense industry , Fracture (Materials)

Universal Weight Function Consistent Method to Fit Polynomial Stress Distribution for Calculation of Stress Intensity Factor

Douglas A. Scarth, Steven X. Xu

PVP 2010; 51-65https://doi.org/10.1115/PVP2010-25728

Abstract

View Articletitled, Universal Weight Function Consistent Method to Fit Polynomial Stress Distribution for Calculation of Stress Intensity Factor

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Topics: Polynomials , Stress , Stress concentration , Weight (Mass) , Wall thickness , Natural, scientific and engineering processes and practices , Computer software , Pressure

Alternate Flaw Acceptance Criterial for Flaws in Ferritic Steel Vessels Operating in the Upper Shelf Range

H. L. Gustin, R. C. Cipolla, D. A. Scarth

PVP 2010; 67-72https://doi.org/10.1115/PVP2010-25741

Abstract

View Articletitled, Alternate Flaw Acceptance Criterial for Flaws in Ferritic Steel Vessels Operating in the Upper Shelf Range

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Topics: Steel , Vessels , Ductility , Fracture mechanics , Acceptance criteria , Alloys , Carbon , Failure , Fracture toughness , Low temperature

Technical Basis for Case N-766 Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation of PWR Full Penetration Circumferential Nickel Alloy Welds in Class 1 Items

Paul Donavin, S. Marlette, W. Bamford, K. Stuckey, G. Poling

PVP 2010; 73-78https://doi.org/10.1115/PVP2010-26164

Abstract

View Articletitled, Technical Basis for Case N-766 Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation of PWR Full Penetration Circumferential Nickel Alloy Welds in Class 1 Items

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Topics: Nickel alloys , Nuclear reactor coolants , Pressurized water reactors , Welded joints , Cracking (Materials) , Fracture (Process) , Maintenance , Coolants , Design , Flow (Dynamics)

Combination of Multi-Axial Loads in Design and Fitness-for-Service Rules

Prediction Method for Plastic Collapse of Pipes Subjected to Combined Bending and Torsion Moments

Yinsheng Li, Kunio Hasegawa, Phuong H. Hoang, Bostjan Bezensek

PVP 2010; 81-87https://doi.org/10.1115/PVP2010-25101

Abstract

View Articletitled, Prediction Method for Plastic Collapse of Pipes Subjected to Combined Bending and Torsion Moments

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Topics: Collapse , Pipes , Torsion , Failure , ASME Boiler and Pressure Vessel Code , Finite element analysis , Fracture (Materials) , In-service inspection , Japan Society of Mechanical Engineers , Pressure

Effect of Pressure on Plastic Collapse Under the Combined Bending and Torsion Moments for Circumferentially Surface Flawed Pipes

Yinsheng Li, Wataru Ida, Kunio Hasegawa, Bostjan Bezensek, Phuong H. Hoang

PVP 2010; 89-97https://doi.org/10.1115/PVP2010-25102

Abstract

View Articletitled, Effect of Pressure on Plastic Collapse Under the Combined Bending and Torsion Moments for Circumferentially Surface Flawed Pipes

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Topics: Collapse , Pipes , Pressure , Torsion , Failure , Stainless steel , Stress , ASME Boiler and Pressure Vessel Code , Finite element analysis , Fracture (Materials)

Proposal for Inclusion of Torsion in Section XI Flaw Evaluation Procedures for Pipes Containing Surface Crack-Like Flaws

Bostjan Bezensek, Yinsheng Li, Kunio Hasegawa, Phuong H. Hoang

PVP 2010; 99-105https://doi.org/10.1115/PVP2010-25133

Abstract

View Articletitled, Proposal for Inclusion of Torsion in Section XI Flaw Evaluation Procedures for Pipes Containing Surface Crack-Like Flaws

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Topics: Fracture (Materials) , Pipes , Torsion , Stress , Pressure , ASME Boiler and Pressure Vessel Code , Boilers , Finite element analysis , Power stations

Effects of Torsion on Equivalent Bending Moment for Limit Load and EPFM Circumferential Pipe Flaw Evaluations

Phuong H. Hoang, Kunio Hasegawa, Bostjan Bezensek, Yinsheng Li

PVP 2010; 107-122https://doi.org/10.1115/PVP2010-25283

Abstract

View Articletitled, Effects of Torsion on Equivalent Bending Moment for Limit Load and EPFM Circumferential Pipe Flaw Evaluations

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Topics: Pipes , Stress , Torsion , ASME Boiler and Pressure Vessel Code , Finite element analysis , Plastics , Pressure

Elastic-Plastic Analysis and Fatigue Issues in Pressure Vessels

A Hierarchical Finite Element Framework for the Assessment of Pressure Vessels to the ASME III Code

Michael Martin, Lindsay Rawson, David Rice

PVP 2010; 125-135https://doi.org/10.1115/PVP2010-25097

Abstract

View Articletitled, A Hierarchical Finite Element Framework for the Assessment of Pressure Vessels to the ASME III Code

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Topics: Finite element analysis , Pressure vessels , Stress , Design , Nuclear power stations , ASME Boiler and Pressure Vessel Code , Collapse , Failure mechanisms , Fatigue , Fatigue life

Analysis of ASME Codes for Fatigue of Pressure Vessels

Khalil Farhangdoost, Payman Hamrahan

PVP 2010; 137-144https://doi.org/10.1115/PVP2010-25320

Abstract

View Articletitled, Analysis of ASME Codes for Fatigue of Pressure Vessels

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Topics: ASME Standards , Fatigue , Pressure vessels , Fracture (Materials) , Stress , Fatigue life , Finite element methods , Nozzles , Computer software , Fatigue analysis

Expressions of Load and Structural Deformation Relationship for Cylindrical and Spherical Vessels Under Internal Pressure

Yang-chun Deng, Gang Chen

PVP 2010; 145-151https://doi.org/10.1115/PVP2010-25648

Abstract

View Articletitled, Expressions of Load and Structural Deformation Relationship for Cylindrical and Spherical Vessels Under Internal Pressure

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Topics: Deformation , Pressure , Stress , Vessels , Pressure vessels , Design , Load bearing capacity , Stress-strain relations , Work hardening

Emerging Codes and Standards

Recent Progress of the Stationary Pressure Vessel Regulations and Standards in China

Binan Shou, Gang Chen, Tiejun Xie

PVP 2010; 155-159https://doi.org/10.1115/PVP2010-25308

Abstract

View Articletitled, Recent Progress of the Stationary Pressure Vessel Regulations and Standards in China

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Topics: China , Pressure vessels , Regulations

Recent Activity of KEPIC Application for Construction and Operation of Nuclear Power Plants in Korea

Hoonseok Byun, Jonghae Kim, Youngho Son, Banuk Park

PVP 2010; 161-166https://doi.org/10.1115/PVP2010-25530

Abstract

View Articletitled, Recent Activity of KEPIC Application for Construction and Operation of Nuclear Power Plants in Korea

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Topics: Construction , Nuclear power stations , Design , Electricity (Physics) , ASME Boiler and Pressure Vessel Code , Engineering standards , Heat treating (Metalworking) , Inspection , Maintenance , Reliability

Classification Method in Chinese Supervision Regulation on Safety Technology for Stationary Pressure Vessel

Linlin Wu, Binan Shou, Tiejun Xie, Zhaohui Chen, Ping Xu

PVP 2010; 167-173https://doi.org/10.1115/PVP2010-25906

Abstract

View Articletitled, Classification Method in Chinese Supervision Regulation on Safety Technology for Stationary Pressure Vessel

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Topics: Pressure vessels , Safety

Using Industry Standards for Designing Composite Repair Systems for Corroded Process Piping

Chris Alexander, Franz Worth

PVP 2010; 175-184https://doi.org/10.1115/PVP2010-25923

Abstract

View Articletitled, Using Industry Standards for Designing Composite Repair Systems for Corroded Process Piping

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Topics: Composite materials , Design , Engineering standards , Maintenance , Process piping , Pipelines , Pipes , Steel , Stiffness

Flexibility Factors for High Density Polyethylene Elbows

Rudolph J. Scavuzzo, Charles N. Papadelis, Siegrid Hall

PVP 2010; 185-196https://doi.org/10.1115/PVP2010-25945

Abstract

View Articletitled, Flexibility Factors for High Density Polyethylene Elbows

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Topics: ASME Boiler and Pressure Vessel Code , Deflection , Deformation , Density , Displacement , Displacement measurement , Euler-Bernoulli beam theory , Geometry , Rotation , Testing

High-Energy Piping Systems are Now Covered Piping Systems

Joseph Frey

PVP 2010; 197-200https://doi.org/10.1115/PVP2010-26069

Abstract

View Articletitled, High-Energy Piping Systems are Now Covered Piping Systems

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Topics: Piping systems , Maintenance , Damage , Design , Failure , Pipes , Power Piping Code , Risk , Wounds

Environmental Fatigue Issues

A Study on the Temperature Calibration for a Small Electrical Resistance Furnace

Un Bong Baek, Hae Moo Lee, Yun-Hee Lee, Seung Hoon Nahm

PVP 2010; 203-207https://doi.org/10.1115/PVP2010-25181

Abstract

View Articletitled, A Study on the Temperature Calibration for a Small Electrical Resistance Furnace

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Topics: Calibration , Electrical resistance , Furnaces , Temperature , High temperature , Fatigue , Low cycle fatigue , Power stations , Temperature control , Thermal stresses

Effects of Continuous Strain Rate Changing on Environmental Fatigue for Stainless Steels in PWR Environment

Yuichiro Nomura, Seiji Asada, Takao Nakamura, Masakazu Tanaka

PVP 2010; 209-214https://doi.org/10.1115/PVP2010-25194

Abstract

View Articletitled, Effects of Continuous Strain Rate Changing on Environmental Fatigue for Stainless Steels in PWR Environment

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Topics: Fatigue , Pressurized water reactors , Stainless steel , Fatigue life , Fatigue testing , Waves , Boiling water reactors , Transients (Dynamics) , Water

Thermal Aging Effect on Environmental Fatigue Life of CF8M Cast Stainless Steel at Strain Rate 0.04%/s Under PWR Operating Condition

Ill-Seok Jeong, Wan-Jae Kim, Hyun-Ik Jeon

PVP 2010; 215-219https://doi.org/10.1115/PVP2010-25564

Abstract

View Articletitled, Thermal Aging Effect on Environmental Fatigue Life of CF8M Cast Stainless Steel at Strain Rate 0.04%/s Under PWR Operating Condition

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Topics: Fatigue life , Pressurized water reactors , Stainless steel , Fatigue , Cycles , Design , Fatigue testing , Life testing , Low cycle fatigue , Nuclear power stations

Status Report on ASME Section III Subgroup on Design Plan for Code Changes to Implement Environmental Fatigue Evaluation Methods

Jack R. Cole, John C. Minichiello

PVP 2010; 221-225https://doi.org/10.1115/PVP2010-25677

Abstract

View Articletitled, Status Report on ASME Section III Subgroup on Design Plan for Code Changes to Implement Environmental Fatigue Evaluation Methods

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Topics: Design , Evaluation methods , Fatigue , Water , ASME Standards , Fatigue life , Nuclear industry , Nuclear reactor coolants , Pressure

Strain Rate Calculation Approach in Environmental Fatigue Evaluations

Mark A. Gray, Matthew C. Salac, David H. Roarty, E. Lyles Cranford, III

PVP 2010; 227-232https://doi.org/10.1115/PVP2010-25947

Abstract

View Articletitled, Strain Rate Calculation Approach in Environmental Fatigue Evaluations

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Topics: Fatigue , ASME Standards , Fatigue analysis , Licensing , Nuclear power stations , Plant design , Water

Effect of Loading Signal Shape and of Surface Finish on the Low Cycle Fatigue Behavior of 304L Stainless Steel in PWR Environment

Jean Alain Le Duff, Andre´ Lefranc¸ois, Jean Philippe Vernot, Delphine Bossu

PVP 2010; 233-241https://doi.org/10.1115/PVP2010-26027

Abstract

View Articletitled, Effect of Loading Signal Shape and of Surface Finish on the Low Cycle Fatigue Behavior of 304L Stainless Steel in PWR Environment

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Topics: Finishes , Low cycle fatigue , Pressurized water reactors , Shapes , Signals , Stainless steel , Temperature , Fatigue analysis , Fatigue design , Fatigue life

Fusion Reactor Component Rules for Structural Integrity

ASME Division IV Magnetic Confinement Fusion Energy Devices

William Sowder, Richard W. Barnes

PVP 2010; 245-247https://doi.org/10.1115/PVP2010-25128

Abstract

View Articletitled, ASME Division IV Magnetic Confinement Fusion Energy Devices

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Topics: Magnetic fusion , Engineering standards , Vessels , Construction , Containment , Design , Inspection , Manufacturing , Metal stamping , Nonmetallic materials

Evaluation of Strength on Dissimilar Metal Joints for ITER First Wall Components

H. Nishi, M. Enoeda, T. Hirose, D. Tsuru, H. Tanigawa

PVP 2010; 249-256https://doi.org/10.1115/PVP2010-26008

Abstract

View Articletitled, Evaluation of Strength on Dissimilar Metal Joints for ITER First Wall Components

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Topics: Armor , Bonding , Cooling , Copper alloys , Electromagnetic force , Fatigue life , Finite element methods , Finite element model , Fracture (Materials) , Fracture (Process)

Current Fusion Standards and Other Related Activities in Japan

Yuji Nakasone, Kazuyoshi Sato, Yukio Takahashi

PVP 2010; 257-261https://doi.org/10.1115/PVP2010-26116

Abstract

View Articletitled, Current Fusion Standards and Other Related Activities in Japan

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Topics: Construction , Japan Society of Mechanical Engineers , Leakage , Manufacturing , Nondestructive evaluation , Nuclear fusion , Pressure , Structural design , Superconducting magnets , Testing

Manufacturing Technologies of Breeding Blanket Components Using Reduced Activation Ferritic/Martensitic Steel

Takanori Hirose, Hiroyasu Tanigawa, Mikio Enoeda

PVP 2010; 263-266https://doi.org/10.1115/PVP2010-26123

Abstract

View Articletitled, Manufacturing Technologies of Breeding Blanket Components Using Reduced Activation Ferritic/Martensitic Steel

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Topics: Manufacturing technology , Martensitic steel , Fibers , Fusion reactors , Hot pressing , Lasers , Specialty steels , Thin wall structures , Water , Welding

Harmonization for Material Data Among Fitness-for-Service Codes

Outline of the JSME Mandatory Rules for Thermal Power Generation Facilities as the Harmonized Code in the Regulatory Requirements

Kazuhiro Kimura, Seiichi Hamada, Masaaki Fujita

PVP 2010; 269-273https://doi.org/10.1115/PVP2010-25119

Abstract

View Articletitled, Outline of the JSME Mandatory Rules for Thermal Power Generation Facilities as the Harmonized Code in the Regulatory Requirements

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Topics: Japan Society of Mechanical Engineers , Regulations , Thermal energy , ASME Standards , Economics , Pipes

Toward International Harmonization of Nuclear Codes and Standards

Claude Faidy

PVP 2010; 275-281https://doi.org/10.1115/PVP2010-25187

Abstract

View Articletitled, Toward International Harmonization of Nuclear Codes and Standards

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Topics: Design , Engineering standards , Manufacturing , Licensing , Pressure , Pressure equipment , Regulations , Safety , Vessels

Assessment of Fatigue Crack Growths for Transformed Surface Flaws Using FFS Codes

Kunio Hasegawa, Yinsheng Li

PVP 2010; 283-288https://doi.org/10.1115/PVP2010-25247

Abstract

View Articletitled, Assessment of Fatigue Crack Growths for Transformed Surface Flaws Using FFS Codes

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Topics: Fatigue cracks , Fitness-for-service

Comparison of Fatigue Crack Growth Curves of Japan, the US and EU Code and Standards

Kiminobu Hojo, Yukio Takahashi

PVP 2010; 289-293https://doi.org/10.1115/PVP2010-25939

Abstract

View Articletitled, Comparison of Fatigue Crack Growth Curves of Japan, the US and EU Code and Standards

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Topics: Fatigue cracks , Steel , ASME Standards , Fracture (Materials) , Japan Society of Mechanical Engineers , Maintenance , Metals , Nuclear power plant maintenance

High Temperature Codes and Standards

Applications of Code Case 2605 for Fatigue Evaluation of Vessels Made in 2.25Cr-1Mo-0.25V Steels Slightly Into Creep Range

Susumu Terada

PVP 2010; 297-306https://doi.org/10.1115/PVP2010-25258

Abstract

View Articletitled, Applications of Code Case 2605 for Fatigue Evaluation of Vessels Made in 2.25Cr-1Mo-0.25V Steels Slightly Into Creep Range

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Topics: Creep , Fatigue , Steel , Vessels , Inelastic analysis , Temperature , Design , Nozzles , Pressure , ASME Standards

Evaluation of Creep-Fatigue Damage for Prototype Process Heat Exchanger of the NHDD Plant

Hyeong-Yeon Lee, Kee-Nam Song, Yong-Wan Kim, Sung-Deok Hong, Hong-Yune Park

PVP 2010; 307-313https://doi.org/10.1115/PVP2010-25354

Abstract

View Articletitled, Evaluation of Creep-Fatigue Damage for Prototype Process Heat Exchanger of the NHDD Plant

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Topics: Creep , Damage , Engineering prototypes , Fatigue , Heat exchangers , Alloys , High temperature , Finite element analysis , Pressure , Temperature

Proposals of Guidelines for High Temperature Structural Design of Fast Reactor Vessels

Naoto Kasahara, Kenichiro Satoh, Kazuyuki Tsukimori, Nobuchika Kawasaki

PVP 2010; 315-322https://doi.org/10.1115/PVP2010-25414

Abstract

View Articletitled, Proposals of Guidelines for High Temperature Structural Design of Fast Reactor Vessels

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Topics: Fast neutron reactors , High temperature , Structural design , Vessels , Design , Creep , Reactor vessels , Stress , Fatigue , Modeling

Verification of the Prediction Methods of Strain Range in Notched Specimens Made of Mod.9Cr-1Mo

Masanori Ando, Yuichi Hirose, Shingo Date, Sota Watanabe, Yasuhiro Enuma, Nobuchika Kawasaki

PVP 2010; 323-334https://doi.org/10.1115/PVP2010-25489

Abstract

View Articletitled, Verification of the Prediction Methods of Strain Range in Notched Specimens Made of Mod.9Cr-1Mo

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Topics: Creep , Damage , Deformation , Design , Electromagnetic induction , Fatigue , Fatigue life , Fatigue testing , Finite element analysis , Fracture (Materials)

Stress and Strain Locus of Perforated Plate in Inelastic Deformation: Strain-Controlled Loading Case

Osamu Watanabe, Bopit Bubphachot, Akihiro Matsuda

PVP 2010; 335-343https://doi.org/10.1115/PVP2010-25556

Abstract

View Articletitled, Stress and Strain Locus of Perforated Plate in Inelastic Deformation: Strain-Controlled Loading Case

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Topics: Deformation , Stress , Finite element analysis , Fatigue , Stress concentration , Creep , Engineering standards , Tension

Interaction and Flaw Modeling for Multiple Flaws

An Engineering Approach to Characterisation of Twin Flaws in Cleavage

Bostjan Bezensek, John Sharples, Mark Wilkes

PVP 2010; 347-354https://doi.org/10.1115/PVP2010-25134

Abstract

View Articletitled, An Engineering Approach to Characterisation of Twin Flaws in Cleavage

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Topics: Deformation , Failure , Fatigue , Finite element analysis , Fitness-for-service , Fracture (Materials) , Geometry , Plasticity

Behavior of Plastic Collapse Moments for Pipes With Two Non-Aligned Flaws

Kunio Hasegawa, Katumasa Miyazaki, Koichi Saito

PVP 2010; 355-361https://doi.org/10.1115/PVP2010-25199

Abstract

View Articletitled, Behavior of Plastic Collapse Moments for Pipes With Two Non-Aligned Flaws

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Topics: Collapse , Pipes , Stress , Exterior walls , Failure , Fitness-for-service , Shapes , Stainless steel , Temperature

Growth Behavior of Two Interacting Surface Cracks of Dissimilar Size (Comparison for Tensile and Bending Load)

Masayuki Kamaya, Masanori Kikuchi, Eiichi Miyokawa

PVP 2010; 363-370https://doi.org/10.1115/PVP2010-25317

Abstract

View Articletitled, Growth Behavior of Two Interacting Surface Cracks of Dissimilar Size (Comparison for Tensile and Bending Load)

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Topics: Stress , Surface cracks , Fracture (Materials) , Shapes , Finite element analysis , Finite element methods , Finite element model , Fitness-for-service

Simulation of Ductile Fracture for Multiple Flaws

Masanori Kikuchi, Kazuhiro Suga, Shota Kawasaki

PVP 2010; 371-377https://doi.org/10.1115/PVP2010-25453

Abstract

View Articletitled, Simulation of Ductile Fracture for Multiple Flaws

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Topics: Ductile fracture , Simulation , Fracture (Materials) , Displacement , Evaluation methods , Stress

Fracture Assessment of Austenitic Stainless Steel Piping With Multiple Flaws in Heat-Affected Zone

Chihiro Narazaki, Toshiyuki Saito, Masao Itatani, Takuya Ogawa, Takao Sasayama

PVP 2010; 379-382https://doi.org/10.1115/PVP2010-25497

Abstract

View Articletitled, Fracture Assessment of Austenitic Stainless Steel Piping With Multiple Flaws in Heat-Affected Zone

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Topics: Fracture (Materials) , Fracture (Process) , Heat , Pipes , Stainless steel , Carbon , Fitness-for-service , JSME Standards , Nuclear power stations , Stress

Coalescence of Complex Cracks in Ex-Service Carbon Steel Pipe Bends During Burst Pressure Tests

Xinjian Duan, Michael J. Kozluk, Tracy Gendron, John Slade

PVP 2010; 383-397https://doi.org/10.1115/PVP2010-25992

Abstract

View Articletitled, Coalescence of Complex Cracks in Ex-Service Carbon Steel Pipe Bends During Burst Pressure Tests

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Topics: Carbon steel , Fracture (Materials) , Pipe bends , Pressure , Failure , Collapse , Design , Pipes , Power stations

Multi-Axial Fatigue Behavior of Vessel and Piping Materials for Design and Evaluation Rules

Crack Growth Analysis in Weld-Heat Affected Zone Using S-Version FEM

Masanori Kikuchi, Yoshitaka Wada, Yuto Shimizu, Yulong Li

PVP 2010; 401-406https://doi.org/10.1115/PVP2010-25154

Abstract

View Articletitled, Crack Growth Analysis in Weld-Heat Affected Zone Using S-Version FEM

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Topics: Finite element methods , Finite element model , Fracture (Materials) , Heat , Stress , Fracture (Process) , Welding , Computer simulation , Machinery , Nuclear power

Effect of K_III on Fatigue Crack Growth Behavior

Masanori Kikuchi, Yoshitaka Wada, Chikako Ohdama

PVP 2010; 407-413https://doi.org/10.1115/PVP2010-25197

Abstract

View Articletitled, Effect of K<sub>III</sub> on Fatigue Crack Growth Behavior

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Topics: Fatigue cracks , Fracture (Materials) , Roofs , Finite element methods , Fatigue testing , Simulation , Surface cracks

Closure Effect on Interaction of Two Surface Cracks Under Cyclic Bending

Masanori Kikuchi, Yoshitaka Wada, Maigefeireti Maitireyimu, Hirotaka Sano

PVP 2010; 415-421https://doi.org/10.1115/PVP2010-25241

Abstract

View Articletitled, Closure Effect on Interaction of Two Surface Cracks Under Cyclic Bending

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Topics: Surface cracks , Fracture (Materials) , Fatigue , Fatigue cracks , Fatigue life , Finite element methods , Finite element model , Stress

Fatigue Behavior of Circumferentially Notched Round Bars of Austenitic Stainless Steel Under Torsional and Axial Loads

Masao Itatani, Keisuke Tanaka, Isao Ohkawa, Takehisa Yamada, Toshiyuki Saito

PVP 2010; 423-431https://doi.org/10.1115/PVP2010-25472

Abstract

View Articletitled, Fatigue Behavior of Circumferentially Notched Round Bars of Austenitic Stainless Steel Under Torsional and Axial Loads

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Topics: Fatigue , Stainless steel , Stress , Stress concentration , Tension , Torsion , Fatigue life , Fracture (Materials) , Crack propagation , Electric potential

On Mixed Mode Crack Propagation Analysis Based on VCCM (Virtual Crack Closure-Integral Method) for Tetrahedral Finite Element

Hiroshi Okada, Hiroshi Kawai, Takashi Tokuda, Yasuyoshi Fukui

PVP 2010; 433-442https://doi.org/10.1115/PVP2010-25527

Abstract

View Articletitled, On Mixed Mode Crack Propagation Analysis Based on VCCM (Virtual Crack Closure-Integral Method) for Tetrahedral Finite Element

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Topics: Crack propagation , Finite element analysis , Fracture (Materials) , Mesh generation , Solids

Experimental Investigations of Fatigue Crack Propagation for Pipe Under Torsional Loading

Motoki Nakane, Satoshi Kanno, Shota Hashimoto, Takayuki Watanabe, Yukio Takahashi

PVP 2010; 443-450https://doi.org/10.1115/PVP2010-25831

Abstract

View Articletitled, Experimental Investigations of Fatigue Crack Propagation for Pipe Under Torsional Loading

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Topics: Fatigue cracks , Pipes , Fracture (Materials) , Stress , Japan Society of Mechanical Engineers , Carbon steel , Dimensions , Fatigue testing , Finite element methods , Finite element model

Numerical 3-D Fatigue Crack Growth Analyses of Real-Life Components

Daniel Bremberg, Guido Dhondt

PVP 2010; 451-458https://doi.org/10.1115/PVP2010-25950

Abstract

View Articletitled, Numerical 3-D Fatigue Crack Growth Analyses of Real-Life Components

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Topics: Fatigue cracks , Fracture (Materials) , Algorithms , Computation , Finite element methods , Fracture mechanics , Modeling

A Study on Behavior of Mixed Mode Fatigue Crack Growth of Spiral Welding Part Under Bending Load

Jung-Hun Choi, Il-Hwan Kim, Jae-Mean Koo, Chang-Sung Seok

PVP 2010; 459-463https://doi.org/10.1115/PVP2010-25972

Abstract

View Articletitled, A Study on Behavior of Mixed Mode Fatigue Crack Growth of Spiral Welding Part Under Bending Load

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Topics: Fatigue cracks , Stress , Welding , Pipes , Steel , Fracture (Materials) , Base metals , Failure , Fracture mechanics , Heat

Low Cycle Fatigue Life of Type 316 Stainless Steel Notched Specimen Under Proportional and Non-Proportional Multiaxial Loadings

Takamoto Itoh

PVP 2010; 465-471https://doi.org/10.1115/PVP2010-25996

Abstract

View Articletitled, Low Cycle Fatigue Life of Type 316 Stainless Steel Notched Specimen Under Proportional and Non-Proportional Multiaxial Loadings

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Topics: Low cycle fatigue , Stainless steel , Shear (Mechanics) , Stress concentration , Temperature , Torsion

Multiaxial Fatigue Failure Criterion Considering Formation and Growth of Small Cracks

Yukio Takahashi

PVP 2010; 473-480https://doi.org/10.1115/PVP2010-26015

Abstract

View Articletitled, Multiaxial Fatigue Failure Criterion Considering Formation and Growth of Small Cracks

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Topics: Failure , Fatigue , Fatigue failure , Fatigue life , Fatigue testing , Fracture (Materials) , Shear (Mechanics) , Stress

Probabilistic and Risk Base Assessment for Codes and Standards

Effects of Several Factors on the Solution of Failure Probability of Pipes in Nuclear Power Plants

Jai Hak Park, Jae Bong Lee, Young Hwan Choi

PVP 2010; 483-489https://doi.org/10.1115/PVP2010-25240

Abstract

View Articletitled, Effects of Several Factors on the Solution of Failure Probability of Pipes in Nuclear Power Plants

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Topics: Failure , Nuclear power stations , Pipes , Probability , Fracture (Materials) , Stress , Leakage , Fatigue , Operating temperature , Simulation

Incorporation of Materials’ Sensitive Simulation Technique Into the PINTIN-CAM Code for Integrity of Nuclear Piping System

Debashis Datta, Changheui Jang

PVP 2010; 491-498https://doi.org/10.1115/PVP2010-25395

Abstract

View Articletitled, Incorporation of Materials’ Sensitive Simulation Technique Into the PINTIN-CAM Code for Integrity of Nuclear Piping System

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Topics: Piping systems , Simulation , Fracture (Materials) , Failure , Fatigue , Stress corrosion cracking , Design , Fracture mechanics , Nozzles , Pressurized water reactors

Analysis Method of Failure Likelihood on Pressure Equipment With Combined Action of Multi-Failure Mechanism

Xuedong Chen, Zhibin Ai, Tiecheng Yang, Jiushao Hu, Chuanqing Cheng

PVP 2010; 499-504https://doi.org/10.1115/PVP2010-25665

Abstract

View Articletitled, Analysis Method of Failure Likelihood on Pressure Equipment With Combined Action of Multi-Failure Mechanism

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Topics: Failure , Pressure equipment , American Petroleum Institute , Failure mechanisms , Risk assessment , China , Petrochemicals , Risk , Accidents , Computational methods

Failure Probability Analysis by Probabilistic Fracture Mechanics Based on FRI SCC Model

Noriyoshi Maeda, Tetsuo Shoji

PVP 2010; 505-512https://doi.org/10.1115/PVP2010-25917

Abstract

View Articletitled, Failure Probability Analysis by Probabilistic Fracture Mechanics Based on FRI SCC Model

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Topics: Failure , Fracture mechanics , Probability , Fracture (Materials) , Corrosion , Electric current , Stress , Coulomb's law , Iterative methods , Log normal distribution

Partial Safety Factors Assessment of Pipes With a Circumferential Surface Flaw

Hideo Machida, Hiromasa Chitose, Manabu Arakawa

PVP 2010; 513-520https://doi.org/10.1115/PVP2010-25993

Abstract

View Articletitled, Partial Safety Factors Assessment of Pipes With a Circumferential Surface Flaw

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Topics: Pipes , Safety , Stress , Fitness-for-service , Fracture (Materials) , Fracture (Process) , Chaos , Design methodology , Materials properties , Reliability

Study on PWSCC Behaviors at Nickel-Based Alloy Welds Based on Weld Residual Stress Analysis and Probabilistic Fracture Mechanics

Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa

PVP 2010; 521-529https://doi.org/10.1115/PVP2010-26028

Abstract

View Articletitled, Study on PWSCC Behaviors at Nickel-Based Alloy Welds Based on Weld Residual Stress Analysis and Probabilistic Fracture Mechanics

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Topics: Alloys , Fracture mechanics , Nickel , Stress analysis (Engineering) , Welded joints , Fracture (Materials) , Stress , Stress corrosion cracking , Boiling water reactors , Electromagnetic scattering

Ratcheting Issues in Pressure Vessel Design

Ratcheting Assessment of a Fixed Tube Sheet Heat Exchanger Subject to In Phase Pressure and Temperature Cycles

Donald Mackenzie, Khosrow Behseta, Robert Hamilton

PVP 2010; 533-539https://doi.org/10.1115/PVP2010-25415

Abstract

View Articletitled, Ratcheting Assessment of a Fixed Tube Sheet Heat Exchanger Subject to In Phase Pressure and Temperature Cycles

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Topics: Cycles , Heat exchangers , Pressure , Temperature , Stress , Vessels , Work hardening , Collapse , Deformation , Design

Review and Assessment of Ratcheting Considerations for Design and Analysis

Yogendra S. Garud

PVP 2010; 541-544https://doi.org/10.1115/PVP2010-25753

Abstract

View Articletitled, Review and Assessment of Ratcheting Considerations for Design and Analysis

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Topics: Creep , Deformation , Design , Hardening , Kinematics , Plasticity , Relaxation (Physics) , Stress , Work hardening

Effect of Ovality on Shakedown of Pipe Bends

Ali Asadkarami, Wolf Reinhardt, Nima Zobeiry

PVP 2010; 545-553https://doi.org/10.1115/PVP2010-25761

Abstract

View Articletitled, Effect of Ovality on Shakedown of Pipe Bends

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Topics: Pipe bends , Stress , ASME Standards , Manufacturing , Pressure

Non-Cyclic Shakedown-Ratcheting Boundary Determination: Analytical Examples

R. Adibi-Asl, W. Reinhardt

PVP 2010; 555-563https://doi.org/10.1115/PVP2010-25911

Abstract

View Articletitled, Non-Cyclic Shakedown-Ratcheting Boundary Determination: Analytical Examples

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Topics: Design , Pressure vessels , Stress , Theorems (Mathematics)

Lower Bound Methods in Elastic-Plastic Shakedown Analysis

Wolf Reinhardt, Reza Adibi-Asl

PVP 2010; 565-573https://doi.org/10.1115/PVP2010-26088

Abstract

View Articletitled, Lower Bound Methods in Elastic-Plastic Shakedown Analysis

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Topics: ASME Standards , Theorems (Mathematics)

Reactor Vessels and Reactor Core Internals for Codes and Standards

Overview of Code Case on Alternative Design Methodology by Using Elastic-Plastic Finite Element Analysis for Class 1 Vessels in the JSME Rules on Design and Construction

Seiji Asada, Takashi Hirano, Tetsuya Nagata, Naoto Kasahara

PVP 2010; 577-584https://doi.org/10.1115/PVP2010-25525

Abstract

View Articletitled, Overview of Code Case on Alternative Design Methodology by Using Elastic-Plastic Finite Element Analysis for Class 1 Vessels in the JSME Rules on Design and Construction

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Topics: Construction , Design , Design methodology , Finite element analysis , Japan Society of Mechanical Engineers , Vessels , Stress , Collapse , Evaluation methods , Elastic analysis

Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel

Jinya Katsuyama, Tohru Tobita, Yutaka Nishiyama, Kunio Onizawa

PVP 2010; 585-592https://doi.org/10.1115/PVP2010-25561

Abstract

View Articletitled, Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel

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Topics: Heat , Reactor vessels , Base metals , Fracture toughness , Grain size , Irradiation (Radiation exposure) , Mechanical properties , Steel , Embrittlement , Surveillance

Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens

Naoki Miura, Naoki Soneda

PVP 2010; 593-602https://doi.org/10.1115/PVP2010-25862

Abstract

View Articletitled, Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens

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Topics: Fracture toughness , Temperature , Steel , ASTM International , Surveillance , Ductile-brittle transition , Electromagnetic scattering , Evaluation methods , Forging , Reactor vessels

Thermal Aging and Neutron Embrittlement Evaluation of Cast Austenitic Stainless Steels

Hardayal S. Mehta, Brian D. Frew, Ronald M. Horn, Fred Hua, Sampath Ranganath, Robert G. Carter

PVP 2010; 603-613https://doi.org/10.1115/PVP2010-25974

Abstract

View Articletitled, Thermal Aging and Neutron Embrittlement Evaluation of Cast Austenitic Stainless Steels

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Topics: Embrittlement , Neutrons , Stainless steel , Inspection , Boiling water reactors , Fracture toughness , Fluence (Radiation measurement) , Licensing , ASME Standards , Couplings

Recent Developments in ASME Codes and Standards

Review of Section VIII, Division 1 and 2 Changes, 2008–2010

Thomas P. Pastor

PVP 2010; 617-623https://doi.org/10.1115/PVP2010-25107

Abstract

View Articletitled, Review of Section VIII, Division 1 and 2 Changes, 2008–2010

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Topics: ASME Boiler and Pressure Vessel Code , Graphite , Pressure vessels , Ultrasonic machining

Development of ASME Section X Code Rules for High Pressure Composite Hydrogen Pressure Vessels With Non-Load Sharing Liners

Norman L. Newhouse, George B. Rawls, Mahendra D. Rana, Bernard F. Shelley, Michael R. Gorman

PVP 2010; 625-634https://doi.org/10.1115/PVP2010-25349

Abstract

View Articletitled, Development of ASME Section X Code Rules for High Pressure Composite Hydrogen Pressure Vessels With Non-Load Sharing Liners

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Topics: Composite materials , High pressure (Physics) , Hydrogen , Pressure vessels , Stress , Vessels , Design , Testing , Acoustic emission testing , Boilers

Technical Basis of Material Toughness Requirements in the ASME B&PV Code, Section VIII, Division 2

David A. Osage, Martin Prager

PVP 2010; 635-652https://doi.org/10.1115/PVP2010-25451

Abstract

View Articletitled, Technical Basis of Material Toughness Requirements in the ASME B&PV Code, Section VIII, Division 2

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Topics: Fracture toughness , Fitness-for-service , American Petroleum Institute , Alloy steel , Carbon , Fracture mechanics , Heat treating (Metalworking) , Impact testing , Joules

Flaw Testing of Fiber Reinforced Composite Pressure Vessels

John Makinson, Norman L. Newhouse

PVP 2010; 653-659https://doi.org/10.1115/PVP2010-25471

Abstract

View Articletitled, Flaw Testing of Fiber Reinforced Composite Pressure Vessels

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Topics: Fiber reinforced composites , Pressure vessels , Testing , Pressure , Composite materials , ASME Standards , Design , Teams , Boilers , Cylinders

An Approach Based on Code Case 2605 for Fatigue Evaluation of Vanadium Modified Materials Reactor

M. Sohel M. Panwala, D. H. Desai, S. L. Mehta

PVP 2010; 661-666https://doi.org/10.1115/PVP2010-25720

Abstract

View Articletitled, An Approach Based on Code Case 2605 for Fatigue Evaluation of Vanadium Modified Materials Reactor

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Topics: Fatigue , Creep , Aeroelasticity , Computer software , Damage , FORTRAN , Design , Junctions , Petroleum , Plastics

Recent Developments in Chinese Codes and Standards

Time-Dependent Risk Control of Crucial Tube Furnace With SIL Requirement Considered

Jianxin Zhu, Xuedong Chen, Zhibin Ai, Weihe Guan

PVP 2010; 669-674https://doi.org/10.1115/PVP2010-25189

Abstract

View Articletitled, Time-Dependent Risk Control of Crucial Tube Furnace With SIL Requirement Considered

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Topics: Furnaces , Instrumentation , Risk , Risk control , Safety

RBI Technology for Boiler Superheater of Power Station

Fujun Liu, Shoubao Ding, Shuai Kong, Dan Song, Dongming Hu, Xiaolian Guo, Nanhui Jin

PVP 2010; 675-682https://doi.org/10.1115/PVP2010-25285

Abstract

View Articletitled, RBI Technology for Boiler Superheater of Power Station

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Topics: Boilers , Power stations , Superheaters , China , Cooling , Erosion , Failure , Failure mechanisms , Fire , Heating

The Typical Steels for Pressure Equipment in China

Shangzhi Zuo, Binan Shou, Guoyi Yang

PVP 2010; 683-687https://doi.org/10.1115/PVP2010-25306

Abstract

View Articletitled, The Typical Steels for Pressure Equipment in China

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Topics: China , Pressure equipment , Steel

Conception and Current Progress of China In-Service Pressure Equipment Inspection and Assessment Regulation and Standard System

Guodong Jia, Binan Shou, Hui Wang, Jin Shi, Guoshan Xie, Haiyi Jiang, Yanze Chen, Zhaohe Chen

PVP 2010; 689-695https://doi.org/10.1115/PVP2010-25316

Abstract

View Articletitled, Conception and Current Progress of China In-Service Pressure Equipment Inspection and Assessment Regulation and Standard System

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Topics: China , Inspection , Pressure equipment

Guidance of Equipment Risk Management With RBI Techniques

Yu Qu, Xiangmin Hao, Anhe Jiang, Mingchao Gao

PVP 2010; 697-702https://doi.org/10.1115/PVP2010-25398

Abstract

View Articletitled, Guidance of Equipment Risk Management With RBI Techniques

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Topics: Risk management , Failure , Inspection , Risk , American Petroleum Institute , China , Computer software , Corrosion , Cycles , Failure mechanisms

Guaranteeing Long-Cycle Safe Operation of Ethylene Plants by RBI Technology

Zhibin Ai, Xuedong Chen, Tiecheng Yang, Jiushao Hu, Chuanqing Cheng

PVP 2010; 703-708https://doi.org/10.1115/PVP2010-25400

Abstract

View Articletitled, Guaranteeing Long-Cycle Safe Operation of Ethylene Plants by RBI Technology

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Topics: Cycles , China , Inspection , Petrochemicals , Industrial capacity , Risk reduction , Risk-based inspection

Numerical Design of Tubesheet Structure Based on Finite Element Analysis

Xiaodong Yu, Caifu Qian, Hongjie Yu

PVP 2010; 709-712https://doi.org/10.1115/PVP2010-25425

Abstract

View Articletitled, Numerical Design of Tubesheet Structure Based on Finite Element Analysis

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Topics: Design , Finite element analysis , Stress , Welding , Deflection , Deformation , Heat exchangers , Pressure , Stiffness

Classification of Defects in Fusion Joints of Polyethylene Pipes

Jinyang Zheng, Yongquan Qin, Jianfeng Shi, Weican Guo, Hui Wang, Fei Wang

PVP 2010; 713-720https://doi.org/10.1115/PVP2010-25576

Abstract

View Articletitled, Classification of Defects in Fusion Joints of Polyethylene Pipes

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Topics: Inspection , Polyethylene pipes

Development of Non-Destructive Test and Safety Assessment of Electrofusion Joints for Connecting Polyethylene Pipes

Jinyang Zheng, Jianfeng Shi, Weican Guo

PVP 2010; 721-729https://doi.org/10.1115/PVP2010-25578

Abstract

View Articletitled, Development of Non-Destructive Test and Safety Assessment of Electrofusion Joints for Connecting Polyethylene Pipes

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Topics: Nondestructive evaluation , Polyethylene pipes , Safety , Welding , Dislocations , Natural gas , Pipes , Ultrasonic testing equipment , Wire

Experimental Investigation on Coupling Focusing Ultrasonic Technique for Inspection of Polyethylene Butt-Fusion Joint

Weican Guo, Jinyang Zheng, Zhongqiang Liu, Jianfeng Shi, Shoubao Ding, Shangzhi Zuo

PVP 2010; 731-736https://doi.org/10.1115/PVP2010-25581

Abstract

View Articletitled, Experimental Investigation on Coupling Focusing Ultrasonic Technique for Inspection of Polyethylene Butt-Fusion Joint

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Topics: Acoustics , Fracture (Materials) , Inspection , Lenses (Optics) , Pipes , Sodium , Speed of sound , Testing , Ultrasonic testing , Water

Effect of Strain Rate on the Deformation-Induced Martensite Transformation and Mechanical Behavior of Austenitic Stainless Steels for Cold Stretched Pressure Vessels

Cunjian Miao, Yaxian Li, Jinyang Zheng

PVP 2010; 737-742https://doi.org/10.1115/PVP2010-25905

Abstract

View Articletitled, Effect of Strain Rate on the Deformation-Induced Martensite Transformation and Mechanical Behavior of Austenitic Stainless Steels for Cold Stretched Pressure Vessels

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Topics: Deformation , Mechanical behavior , Pressure vessels , Stainless steel

A Method for Detecting the Cold Welding and Optimizing the Welding Procedure for the Electro-Fusion Joints in PE Pipes

Ping Xu, Weican Guo, Shoubao Ding, Shangzhi Zuo, Ping Shi

PVP 2010; 743-749https://doi.org/10.1115/PVP2010-25932

Abstract

View Articletitled, A Method for Detecting the Cold Welding and Optimizing the Welding Procedure for the Electro-Fusion Joints in PE Pipes

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Topics: Polyethylene pipes , Welding

Seismic Behavior of Buried PE Pipelines Subject to Fault Offsets

Michael J. O’Rourke, Tarek H. Abdoun, Da Ha

PVP 2010; 751-767https://doi.org/10.1115/PVP2010-26064

Abstract

View Articletitled, Seismic Behavior of Buried PE Pipelines Subject to Fault Offsets

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Topics: Deformation , Hazards , Instrumentation , Pipelines , Pipes , Polyethylene pipes , Pressure , Soil , Springs

Recent Developments in European Codes and Standards

Flaw Evaluation in Elbows Through French RSEM Code

Claude Faidy

PVP 2010; 771-778https://doi.org/10.1115/PVP2010-25085

Abstract

View Articletitled, Flaw Evaluation in Elbows Through French RSEM Code

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Topics: Design , Fitness-for-service , Fracture (Materials) , Fracture toughness , Safety , Stainless steel , Stress-strain curves , Transients (Dynamics)

The Future of the BS 7910 Flaw Assessment Procedures

Isabel Hadley, Bob Ainsworth, Peter Budden, John Sharples

PVP 2010; 779-789https://doi.org/10.1115/PVP2010-25582

Abstract

View Articletitled, The Future of the BS 7910 Flaw Assessment Procedures

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Topics: Corrosion , Creep , Damage , Failure , Fatigue , Fatigue cracks , Fracture (Materials) , Nondestructive evaluation , Pipelines , Stress

VERLIFE: Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation—Updating and Further Development

Milan Brumovsky

PVP 2010; 791-795https://doi.org/10.1115/PVP2010-25624

Abstract

View Articletitled, VERLIFE: Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation—Updating and Further Development

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Topics: Nuclear power stations , Pipes , Reactor vessels , Corrosion , Damage , Design , Erosion , Failure , Fracture mechanics , Leak-before-break

Presentation of the Afcen RCC-MRx Code for Sodium Reactors (SFR), Research Reactors (RR) and Fusion (ITER): General Overview

T. Lebarbe´, S. Marie, B. Drubay, O. Gelineau, D. Bonne, Frantz De La Burgade

PVP 2010; 797-802https://doi.org/10.1115/PVP2010-25673

Abstract

View Articletitled, Presentation of the Afcen RCC-MRx Code for Sodium Reactors (SFR), Research Reactors (RR) and Fusion (ITER): General Overview

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Topics: Aluminum alloys , Construction , Design , High temperature , Irradiation (Radiation exposure) , Materials properties , Sodium , Sodium fast reactors , Zirconium alloys

Codification of 316LN in RCC-MR Code: Experience and Prospective Projects

D. Bonne, S. Dubiez-LeGoff, B. Drubay

PVP 2010; 803-807https://doi.org/10.1115/PVP2010-25679

Abstract

View Articletitled, Codification of 316LN in RCC-MR Code: Experience and Prospective Projects

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Topics: Alloys , Base metals , Breeder reactors , Construction , Creep , Databases , Design , Fast neutron reactors , Fatigue , Feedback

Evolution in the Italian Standard for Creep-Operated Pressure Equipment

Ottaviano Grisolia, Corrado Delle Site

PVP 2010; 809-820https://doi.org/10.1115/PVP2010-25683

Abstract

View Articletitled, Evolution in the Italian Standard for Creep-Operated Pressure Equipment

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Topics: Creep , Pressure equipment , Furnaces , Regulations , Risk-based inspection , Temperature

RCC-M: Content, Working Approach and Future Evolutions

Jean-Marie Grandemange, Philippe Malouines

PVP 2010; 821-835https://doi.org/10.1115/PVP2010-26030

Abstract

View Articletitled, RCC-M: Content, Working Approach and Future Evolutions

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Topics: Construction , Design , Engineering standards , In-service inspection , Pressure equipment , Regulations

Recent Developments in Japanese Codes and Standards

Effect of Overload on the Threshold Stress Intensity Factor Range of SUS316 as a Function of Crack Size

Kotoji Ando, Koji Takahashi, Yasuaki Hashikura, Keiji Houjyou

PVP 2010; 839-843https://doi.org/10.1115/PVP2010-25153

Abstract

View Articletitled, Effect of Overload on the Threshold Stress Intensity Factor Range of SUS316 as a Function of Crack Size

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Topics: Fracture (Materials) , Stress , Fatigue testing

Effect of Shot Peening on Fatigue Limit of Surface Flawed Sample

Kotoji Ando, Fumio Takahashi, Akira Tange, Yoshiki Ono

PVP 2010; 845-850https://doi.org/10.1115/PVP2010-25155

Abstract

View Articletitled, Effect of Shot Peening on Fatigue Limit of Surface Flawed Sample

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Topics: Fatigue limit , Shot peening , Fracture (Materials) , Failure , Fatigue strength , Fatigue testing , Stress

Failure Probability of Degraded Pipes Based on Probabilistic Fracture Mechanics for Seismic Safety Margin Assessment on NPP

Yinsheng Li, Masaki Nakagawa, Katsumi Ebisawa, Shinobu Yoshimura, Hiroyuki Kameda

PVP 2010; 851-859https://doi.org/10.1115/PVP2010-25203

Abstract

View Articletitled, Failure Probability of Degraded Pipes Based on Probabilistic Fracture Mechanics for Seismic Safety Margin Assessment on NPP

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Topics: Failure , Fracture mechanics , Nuclear power stations , Pipes , Probability , Safety , Cooling , Design , Earthquakes , Fatigue

Seismic Safety Margin Assessment for Electrical Components Utilizing Full-Scale Test

Toru Iijima, Masaki Nakagawa, Akira Shibuya, Katsumi Ebisawa, Hiroyuki Kameda

PVP 2010; 861-868https://doi.org/10.1115/PVP2010-25205

Abstract

View Articletitled, Seismic Safety Margin Assessment for Electrical Components Utilizing Full-Scale Test

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Topics: Electrical components , Safety , Earthquakes , Earthquake resistant design , Nuclear power stations , Damage , Design , Failure , Metals , Nuclear power

Seismic Safety Margin Assessment for Thin-Wall Cylindrical Tanks Utilizing Ultimate Strength Test

Toru Iijima, Masaki Nakagawa, Akira Shibuya, Katsumi Ebisawa, Hiroyuki Kameda

PVP 2010; 869-877https://doi.org/10.1115/PVP2010-25206

Abstract

View Articletitled, Seismic Safety Margin Assessment for Thin-Wall Cylindrical Tanks Utilizing Ultimate Strength Test

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Topics: Safety , Tensile strength , Thin wall structures , Earthquakes , Nuclear power stations , Design , Earthquake resistant design , Damage , Failure , Nuclear power

Seismic Safety Margin Assessment for NPP Utilizing Full-Scale Tests: Overview

Hiroyuki Kameda, Masaki Nakagawa, Akira Shibuya, Shiro Fukunishi, Katsumi Ebisawa

PVP 2010; 879-884https://doi.org/10.1115/PVP2010-25253

Abstract

View Articletitled, Seismic Safety Margin Assessment for NPP Utilizing Full-Scale Tests: Overview

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Topics: Nuclear power stations , Safety , Earthquakes , Nuclear power , Seismic hazard assessment

Finite Element Analyses of Residual Stresses in Typical Welded Joints Used in Nuclear Power Plants and Comparisons With Experiments

Dean Deng, Kazuo Ogawa, Nobuyoshi Yanagida, Koichi Saito

PVP 2010; 885-896https://doi.org/10.1115/PVP2010-25321

Abstract

View Articletitled, Finite Element Analyses of Residual Stresses in Typical Welded Joints Used in Nuclear Power Plants and Comparisons With Experiments

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Topics: Computer simulation , Finite element analysis , Nuclear power stations , Residual stresses , Stress , Stress corrosion cracking , Welded joints , Welding , Metals , Boiling water reactors

Damage Observations of the Straight Pipes Subjected to Cyclic Load Amplitudes of Various Levels

Izumi Nakamura, Akihito Otani, Masaki Shiratori

PVP 2010; 897-904https://doi.org/10.1115/PVP2010-25495

Abstract

View Articletitled, Damage Observations of the Straight Pipes Subjected to Cyclic Load Amplitudes of Various Levels

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Topics: Damage , Pipes , Stress , Deflection , Failure , Piping systems , Deformation , Design , Displacement , Earthquake resistant design

Improvement of the Threshold Stress Intensity Factor for Stress Corrosion Cracking in SUS316 by Tensile Overload

Koji Takahashi, Yuji Miyazaki, Yasuaki Hashikura, Kotoji Ando

PVP 2010; 905-910https://doi.org/10.1115/PVP2010-25610

Abstract

View Articletitled, Improvement of the Threshold Stress Intensity Factor for Stress Corrosion Cracking in SUS316 by Tensile Overload

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Topics: Stress , Stress corrosion cracking , Fatigue , Stainless steel , Wedges

Fracture Assessment for Butt Welded Plate of Ni-Based Alloy

Masao Itatani, Takuya Ogawa, Toshiyuki Saito, Chihiro Narazaki, Kazuo Ogawa

PVP 2010; 911-916https://doi.org/10.1115/PVP2010-25645

Abstract

View Articletitled, Fracture Assessment for Butt Welded Plate of Ni-Based Alloy

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Topics: Alloys , Fracture (Materials) , Stress , Fracture (Process) , Collapse , Electrical discharge machining , Plates (structures) , Fatigue , Flow (Dynamics) , Shapes

Crack Branching and Its Effect on Environmentally Assisted Cracking in High Temperature Water Environments

Zhanpeng Lu, He Xue, Tetsuo Shoji

PVP 2010; 917-927https://doi.org/10.1115/PVP2010-25818

Abstract

View Articletitled, Crack Branching and Its Effect on Environmentally Assisted Cracking in High Temperature Water Environments

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Topics: Cracking (Materials) , Fracture (Materials) , Fracture (Process) , High temperature , Water , Stress , Stress corrosion cracking , Alloys , Cantilever beams , Computer simulation

Sensitivity Analysis of Residual Stress Simulation of Dissimilar Metal Joint of Safe End Nozzle and Key Issues for Standard Procedure to Maintenance Rules

Kiminobu Hojo, Kazuo Ogawa, Naoki Ogawa, Itaru Muroya

PVP 2010; 929-939https://doi.org/10.1115/PVP2010-25936

Abstract

View Articletitled, Sensitivity Analysis of Residual Stress Simulation of Dissimilar Metal Joint of Safe End Nozzle and Key Issues for Standard Procedure to Maintenance Rules

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Topics: Maintenance , Metals , Nozzles , Sensitivity analysis , Simulation , Stress , Computer simulation , Fracture (Materials) , Nuclear power , Safety

Fracture Evaluation Using Limit Analysis for Complex Structure (Pressure Load)

Kiminobu Hojo, Mayumi Ochi, Kazuo Ogawa, Naoki Ogawa

PVP 2010; 941-952https://doi.org/10.1115/PVP2010-26114

Abstract

View Articletitled, Fracture Evaluation Using Limit Analysis for Complex Structure (Pressure Load)

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Topics: Fracture (Materials) , Fracture (Process) , Pressure , Stress , Pipes , Nozzles , Evaluation methods , Failure , Materials properties

Ductile Fracture Strength of Ni-Based Alloy With an Inch Thickness

Katsumasa Miyazaki, Koichi Saito

PVP 2010; 953-958https://doi.org/10.1115/PVP2010-26120

Abstract

View Articletitled, Ductile Fracture Strength of Ni-Based Alloy With an Inch Thickness

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Topics: Alloys , Ductile fracture , Stress , Fracture (Materials) , Fracture (Process) , Flat plates , Base metals , Failure , Finite element analysis , Metals

Influencing Factors for Improving Accuracy in Prediction of Stress Corrosion Crack Growth Rate in Boiling Water Reactor Operational Condition: Part 2—The Effect of Single Overload on SCC Growth Behavior

Yuzuru Ito, Masahiro Saito, Qunjia Peng, Jiro Kuniya, Tetsuo Shoji

PVP 2010; 959-967https://doi.org/10.1115/PVP2010-26121

Abstract

View Articletitled, Influencing Factors for Improving Accuracy in Prediction of Stress Corrosion Crack Growth Rate in Boiling Water Reactor Operational Condition: Part 2—The Effect of Single Overload on SCC Growth Behavior

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Topics: Boiling water reactors , Stress corrosion cracking , Testing , Water , Alternating current potential drop techniques , Electrical conductivity , Stress , Water pollution

Influencing Factors for Improving Accuracy in Prediction of Stress Corrosion Crack Growth Rate in Boiling Water Reactor Operational Condition: Part 1—Prediction of SCC Growth Rate in Terms of Vickers Hardness

Yoichi Takeda, Zhanpeng Lu, Takeshi Adachi, Qunjia Peng, Jiro Kuniya, Tetsuo Shoji

PVP 2010; 969-976https://doi.org/10.1115/PVP2010-26135

Abstract

View Articletitled, Influencing Factors for Improving Accuracy in Prediction of Stress Corrosion Crack Growth Rate in Boiling Water Reactor Operational Condition: Part 1—Prediction of SCC Growth Rate in Terms of Vickers Hardness

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Topics: Boiling water reactors , Stress corrosion cracking , Vickers hardness testing , Fracture (Materials) , Work hardening , Yield strength , Cracking (Materials) , Fracture (Process) , Power stations , Stainless steel

Contributory Factors to Accurate Prediction of Rate of Stress Corrosion Cracking in Boiling Water Reactor Under Unexpected Condition During Operation: Part 3—The Effect of High Loading Rate on SCC Growth Behaviour

Yuji Tanabe, Takeo Tamura, Kenji Suzuki, Jiro Kuniya, Tetsuo Shoji

PVP 2010; 977-983https://doi.org/10.1115/PVP2010-26136

Abstract

View Articletitled, Contributory Factors to Accurate Prediction of Rate of Stress Corrosion Cracking in Boiling Water Reactor Under Unexpected Condition During Operation: Part 3—The Effect of High Loading Rate on SCC Growth Behaviour

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Topics: Boiling water reactors , Finite element methods , Pressure , Stainless steel , Stress , Stress corrosion cracking , Tension , Wedges

Recent Developments in Korean Codes and Standards

Low Cycle Fatigue Behavior and Seismic Assessment for Elbow Pipe Having Local Wall Thinning

Yoshio Urabe, Koji Takahashi, Kotoji Ando

PVP 2010; 987-991https://doi.org/10.1115/PVP2010-25612

Abstract

View Articletitled, Low Cycle Fatigue Behavior and Seismic Assessment for Elbow Pipe Having Local Wall Thinning

PDF

Topics: Low cycle fatigue , Pipes , Corrosion , Erosion , Fatigue cracks , Fatigue life , Pressure , Safety , ASME Boiler and Pressure Vessel Code , Displacement

An Investigation on Stress Concentration of Local Wall Thinning in Feeder Elbow Pipe

Jong Sung Kim, Jae Seok Seo

PVP 2010; 993-998https://doi.org/10.1115/PVP2010-25937

Abstract

View Articletitled, An Investigation on Stress Concentration of Local Wall Thinning in Feeder Elbow Pipe

PDF

Topics: Pipes , Stress concentration , Fatigue , Carbon steel , Design , Stress , Corrosion , Finite element analysis , Flow (Dynamics) , Fuels

Diagnostics of Nuclear Power Plant Components Due to Thickness Measurement by Using Digital Radiography

Masahito Mochizuki, Satoshi Kanno, Shunichi Shimizu, Yuichi Daitou

PVP 2010; 999-1006https://doi.org/10.1115/PVP2010-25999

Abstract

View Articletitled, Diagnostics of Nuclear Power Plant Components Due to Thickness Measurement by Using Digital Radiography

PDF

Topics: Nuclear power stations , Thickness measurement , Imaging , Power stations

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

Changes in Section XI: Repairs and Replacements (2007 Through 2009)

Ronald A. Yonekawa, Edward B. Gerlach

PVP 2010; 1009-1013https://doi.org/10.1115/PVP2010-25007

Abstract

View Articletitled, Changes in Section XI: Repairs and Replacements (2007 Through 2009)

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Topics: Maintenance

Development of Stress Reduction Method in the Pipe Welded Zone by Heating

Yuka Fukuda, Shinobu Okido

PVP 2010; 1015-1021https://doi.org/10.1115/PVP2010-25931

Abstract

View Articletitled, Development of Stress Reduction Method in the Pipe Welded Zone by Heating

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Topics: Heating , Pipes , Stress , Stainless steel , Temperature , Carbon , Tension , Countermeasures , Failure , Thermal stresses

Current Status of RRA Rules Development in JSME Fitness-for-Service Code

Koji Dozaki, Satoshi Yamamoto, Koji Koyama

PVP 2010; 1023-1029https://doi.org/10.1115/PVP2010-26117

Abstract

View Articletitled, Current Status of RRA Rules Development in JSME Fitness-for-Service Code

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Topics: Fitness-for-service , Japan Society of Mechanical Engineers , Engineering standards , Inspection , Maintenance , Safety , In-service inspection , Mechanical engineers , Nuclear power

Ambient Temperature Temperbead Welding Using the Underwater Laser Beam Welding Process

Bruce Newton

PVP 2010; 1031-1036https://doi.org/10.1115/PVP2010-26134

Abstract

View Articletitled, Ambient Temperature Temperbead Welding Using the Underwater Laser Beam Welding Process

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Topics: Laser welding , Temperature , Welding , Gas tungsten arc welding , Radiation (Physics) , Machinery , Maintenance , Testing , ASME Standards , Nuclear industry

Structural Integrity of Pressure Components

ASME B31.3 End of Life Considerations: Corrosion, Mechanical Strength, and Small Bore Geometry

Dennis K. Williams

PVP 2010; 1039-1044https://doi.org/10.1115/PVP2010-25009

Abstract

View Articletitled, ASME B31.3 End of Life Considerations: Corrosion, Mechanical Strength, and Small Bore Geometry

PDF

Topics: Clearances (Engineering) , Corrosion , Geometry , Strength (Materials)

Finite Element Analysis of Residual Stresses in Butt Welding of Stainless Steel Plates by GTAW

Gurinder Singh Brar, Rakesh Kumar

PVP 2010; 1045-1048https://doi.org/10.1115/PVP2010-25184

Abstract

View Articletitled, Finite Element Analysis of Residual Stresses in Butt Welding of Stainless Steel Plates by GTAW

PDF

Topics: Butt welding , Finite element analysis , Gas tungsten arc welding , Plates (structures) , Residual stresses , Stainless steel

Safety Classification Informed Structural Integrity Assessment of Nuclear Plant Components

C. D. Bell, C. T. Watson, J. Howson, A. E. Walker

PVP 2010; 1049-1058https://doi.org/10.1115/PVP2010-25309

Abstract

View Articletitled, Safety Classification Informed Structural Integrity Assessment of Nuclear Plant Components

PDF

Topics: Nuclear power stations , Safety , Risk , ASME Boiler and Pressure Vessel Code , Failure , Inspection , Manufacturing

The Role of Research in Standards Development

Dan Andrei

PVP 2010; 1059-1061https://doi.org/10.1115/PVP2010-25697

Abstract

View Articletitled, The Role of Research in Standards Development

PDF

Topics: ASME Standards , Bridges (Structures) , Collaboration , Engineering standards , Governments , Health and safety , Industrial research , Pipes , Regulations

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Combination of Multi-Axial Loads in Design and Fitness-for-Service Rules

Elastic-Plastic Analysis and Fatigue Issues in Pressure Vessels

Emerging Codes and Standards

Environmental Fatigue Issues

Fusion Reactor Component Rules for Structural Integrity

Harmonization for Material Data Among Fitness-for-Service Codes

High Temperature Codes and Standards

Interaction and Flaw Modeling for Multiple Flaws

Multi-Axial Fatigue Behavior of Vessel and Piping Materials for Design and Evaluation Rules

Probabilistic and Risk Base Assessment for Codes and Standards

Ratcheting Issues in Pressure Vessel Design

Reactor Vessels and Reactor Core Internals for Codes and Standards

Recent Developments in ASME Codes and Standards

Recent Developments in Chinese Codes and Standards

Recent Developments in European Codes and Standards

Recent Developments in Japanese Codes and Standards

Recent Developments in Korean Codes and Standards

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

Structural Integrity of Pressure Components

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