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ASME 2003 Pressure Vessels and Piping Conference

July 20–24, 2003

Cleveland, Ohio, USA

Conference Sponsors:

ISBN:

0-7918-4154-5

In This Volume

Flaw Evaluation, Service Experience, and Reliability

Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Components in ASME Code Section XI

Russell C. Cipolla, Guy H. DeBoo, Warren H. Bamford, Jr., Kenneth K. Yoon, Kunio K. Hasegawa

PVP 2003; 3-18https://doi.org/10.1115/PVP2003-2022

Abstract

View Articletitled, Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Components in ASME Code Section XI

PDF

Topics: Acceptance criteria , ASME Standards , Pressure , Leakage , Nuclear power stations , ASME Boiler and Pressure Vessel Code , Failure , In-service inspection , Mechanical engineers , Nuclear reactor coolants

Developments in the Flaw Assessment Procedures of R6 Revision 4 and BS7910

R. A. Ainsworth, P. J. Budden, A. R. Dowling, J. K. Sharples

PVP 2003; 19-25https://doi.org/10.1115/PVP2003-2023

Abstract

View Articletitled, Developments in the Flaw Assessment Procedures of R6 Revision 4 and BS7910

PDF

Topics: Creep , Temperature

General Presentation of French Codified Flaw Evaluation Procedure: RSE-M

Claude Faidy

PVP 2003; 27-38https://doi.org/10.1115/PVP2003-2024

Abstract

View Articletitled, General Presentation of French Codified Flaw Evaluation Procedure: RSE-M

PDF

Topics: Brittleness , Fatigue , Fatigue cracks , Fracture (Materials) , Fracture (Process) , In-service inspection , Maintenance , Materials properties , Nuclear power stations , Pressure equipment

Flaw Evaluation and Allowable Flaw Sizes of Nuclear Piping in JSME Code

Kunio Hasegawa, Hideo Kobayashi, Koichi Kashima

PVP 2003; 39-44https://doi.org/10.1115/PVP2003-2025

Abstract

View Articletitled, Flaw Evaluation and Allowable Flaw Sizes of Nuclear Piping in JSME Code

PDF

Topics: JSME Standards , Pipes , Acceptance criteria , Inspection , Japan Society of Mechanical Engineers , In-service inspection , Mechanical engineers , Nuclear power stations

Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Piping in ASME Code Section XI

Douglas A. Scarth, Gery M. Wilkowski, Russell C. Cipolla, Sushil K. Daftuar, Koichi K. Kashima

PVP 2003; 45-61https://doi.org/10.1115/PVP2003-2026

Abstract

View Articletitled, Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Piping in ASME Code Section XI

PDF

Topics: Acceptance criteria , ASME Standards , Pipes , Fracture mechanics , Piping systems , Stress , ASME Boiler and Pressure Vessel Code , Brittle fracture , Collapse , Failure

A New Combined Deterministic and Probabilistic Flaw Evaluation Procedure

Peter Dillstro¨m

PVP 2003; 63-70https://doi.org/10.1115/PVP2003-2027

Abstract

View Articletitled, A New Combined Deterministic and Probabilistic Flaw Evaluation Procedure

PDF

Topics: Computer software , Fracture (Materials) , Residual stresses , Safety , Stress

API 579: A Comprehensive Fitness-for-Service Standard

David A. Osage

PVP 2003; 71-84https://doi.org/10.1115/PVP2003-2028

Abstract

View Articletitled, API 579: A Comprehensive Fitness-for-Service Standard

PDF

Topics: American Petroleum Institute , Fitness-for-service , Damage , ASME Standards , Engineering standards , In-service inspection , Petrochemicals

Fitness-for-Service Assessment for Pressure Equipment in Japan

Takayasu Tahara

PVP 2003; 85-90https://doi.org/10.1115/PVP2003-2029

Abstract

View Articletitled, Fitness-for-Service Assessment for Pressure Equipment in Japan

PDF

Topics: Fitness-for-service , Pressure equipment , Regulations , American Petroleum Institute , Fracture (Materials) , Maintenance , Petrochemicals , Pressure vessels , Engineering drawing and drafting , High pressure (Physics)

A French Guideline for Defect Assessment at Elevated Temperature and Leak Before Break Analysis

Y. Kayser, S. Marie, M. H. Lacire, S. Chapuliot, B. Drubay

PVP 2003; 91-96https://doi.org/10.1115/PVP2003-2030

Abstract

View Articletitled, A French Guideline for Defect Assessment at Elevated Temperature and Leak Before Break Analysis

PDF

Topics: Leak-before-break , Temperature , Stress , Fracture (Materials) , Creep , Fatigue , Fatigue cracks , Pipes , Plates (structures) , Algorithms

Assessment of Creep and Creep-Fatigue Crack Growth Following the R5 Procedures

R. A. Ainsworth, P. J. Budden, D. W. Dean, M. J. H. Fox, M. P. O’Donnell, J. M. H. Dean, I. W. Goodall, D. G. Hooton

PVP 2003; 97-104https://doi.org/10.1115/PVP2003-2031

Abstract

View Articletitled, Assessment of Creep and Creep-Fatigue Crack Growth Following the R5 Procedures

PDF

Topics: Creep , Fatigue , Fracture (Materials) , High temperature

Defect Assessment Procedure for Low to High Temperature Range

Bilal Dogan, Robert Ainsworth

PVP 2003; 105-111https://doi.org/10.1115/PVP2003-2032

Abstract

View Articletitled, Defect Assessment Procedure for Low to High Temperature Range

PDF

Topics: High temperature , Creep , Fatigue cracks , Fitness-for-service

Probabilistic Predictions for Piping Fatigue Including the Effects of Ultrasonic Examinations

F. A. Simonen

PVP 2003; 115-120https://doi.org/10.1115/PVP2003-2033

Abstract

View Articletitled, Probabilistic Predictions for Piping Fatigue Including the Effects of Ultrasonic Examinations

PDF

Topics: Fatigue , Pipes , Ultrasonic testing , Failure , Stress , Probability , Fatigue cracks , Fracture (Materials) , Inspection , Cycles

Effects of Weld Repairs on Calculated Failure Probabilities for Reactor Pressure Vessels and Piping

F. A. Simonen, G. J. Schuster, S. R. Doctor

PVP 2003; 121-127https://doi.org/10.1115/PVP2003-2034

Abstract

View Articletitled, Effects of Weld Repairs on Calculated Failure Probabilities for Reactor Pressure Vessels and Piping

PDF

Topics: Failure , Maintenance , Pipes , Probability , Reactor vessels , Vessels , Welded joints , Manufacturing , ASME Boiler and Pressure Vessel Code , Brittle fracture

Creep Activation Energy of Electrosleeve™ Nano-Crystalline Nickel–Phosphorous Tube Repair and Ni-200

Mike G. Pop, James E. Galford, John C. Griffith, John A. Burgess

PVP 2003; 129-134https://doi.org/10.1115/PVP2003-2035

Abstract

View Articletitled, Creep Activation Energy of Electrosleeve™ Nano-Crystalline Nickel–Phosphorous Tube Repair and Ni-200

PDF

Topics: Creep , Maintenance , Nickel , Nanocrystals , Alloys , Boilers , Electrodeposition , Engineering design , Materials properties , Pressure

Remote Inspection of a High Level Radioactive Waste Storage Tank for Cracking, Thinning, and Pitting

J. B. Elder, B. J. Wiersma, R. L. Sindelar

PVP 2003; 135-142https://doi.org/10.1115/PVP2003-2036

Abstract

View Articletitled, Remote Inspection of a High Level Radioactive Waste Storage Tank for Cracking, Thinning, and Pitting

PDF

Topics: Cracking (Materials) , Fracture (Process) , Inspection , Radioactive wastes , Storage tanks , Corrosion , Crack detection , Design , Fracture (Materials) , In-service inspection

Structural Impact Assessment of Flaws Detected During Ultrasonic Examination of a Radioactive Waste Tank

B. J. Wiersma, J. B. Elder

PVP 2003; 143-156https://doi.org/10.1115/PVP2003-2037

Abstract

View Articletitled, Structural Impact Assessment of Flaws Detected During Ultrasonic Examination of a Radioactive Waste Tank

PDF

Topics: Radioactive wastes , Ultrasonic testing , Fracture (Materials) , Stress corrosion cracking , Inspection , Residual stresses , Vapors , Corrosion , Damage , Hydrostatics

The Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations and Its Application at North Anna Unit 2

W. H. Bamford, L. L. Spain, R. E. Gold, W. R. Gahwiller, J. P. Lareau

PVP 2003; 159-170https://doi.org/10.1115/PVP2003-2038

Abstract

View Articletitled, The Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations and Its Application at North Anna Unit 2

PDF

Topics: Maintenance , Reactor vessels , Cracking (Materials) , Fracture (Process) , Inspection , Welded joints

Pressure Protection Evaluation Program at Savannah River Site

James K. Chan, John W. Ramsey

PVP 2003; 171-177https://doi.org/10.1115/PVP2003-2039

Abstract

View Articletitled, Pressure Protection Evaluation Program at Savannah River Site

PDF

Topics: Pressure , Rivers , Computer software , Design , Safety , American Petroleum Institute , Failure , Inspection , Maintenance , Materials handling

A Fracture Mechanics Evaluation of BWR Shroud Mid-Core Horizontal Weld to Justify Continued Operation

Hardayal S. Mehta, George Inch, Shashi Dhar

PVP 2003; 179-191https://doi.org/10.1115/PVP2003-2040

Abstract

View Articletitled, A Fracture Mechanics Evaluation of BWR Shroud Mid-Core Horizontal Weld to Justify Continued Operation

PDF

Topics: Boiling water reactors , Fracture mechanics , Fluence (Radiation measurement) , Stress , Cracking (Materials) , Fracture (Process) , Ductile fracture , Fracture (Materials) , Inspection , Nuclear fuel cycle

All Years

Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Components in ASME Code Section XI

Developments in the Flaw Assessment Procedures of R6 Revision 4 and BS7910

General Presentation of French Codified Flaw Evaluation Procedure: RSE-M

Flaw Evaluation and Allowable Flaw Sizes of Nuclear Piping in JSME Code

Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Piping in ASME Code Section XI

A New Combined Deterministic and Probabilistic Flaw Evaluation Procedure

API 579: A Comprehensive Fitness-for-Service Standard

Fitness-for-Service Assessment for Pressure Equipment in Japan

A French Guideline for Defect Assessment at Elevated Temperature and Leak Before Break Analysis

Assessment of Creep and Creep-Fatigue Crack Growth Following the R5 Procedures

Defect Assessment Procedure for Low to High Temperature Range

Probabilistic Predictions for Piping Fatigue Including the Effects of Ultrasonic Examinations

Effects of Weld Repairs on Calculated Failure Probabilities for Reactor Pressure Vessels and Piping

Creep Activation Energy of Electrosleeve™ Nano-Crystalline Nickel–Phosphorous Tube Repair and Ni-200

Remote Inspection of a High Level Radioactive Waste Storage Tank for Cracking, Thinning, and Pitting

Structural Impact Assessment of Flaws Detected During Ultrasonic Examination of a Radioactive Waste Tank

The Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations and Its Application at North Anna Unit 2

Pressure Protection Evaluation Program at Savannah River Site

A Fracture Mechanics Evaluation of BWR Shroud Mid-Core Horizontal Weld to Justify Continued Operation

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