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ASME/JSME 2004 Pressure Vessels and Piping Conference

July 25–29, 2004

San Diego, California, USA

Conference Sponsors:

ISBN:

0-7918-4682-2

In This Volume

Aging Management and License Renewal

Piping Service Life Experience in Commercial Nuclear Power Plants: Progress With the OECD Pipe Failure Data Exchange Project

Bengt Lydell, Eric Mathet, Karen Gott

PVP 2004; 5-10https://doi.org/10.1115/PVP2004-2961

Abstract

View Articletitled, Piping Service Life Experience in Commercial Nuclear Power Plants: Progress With the OECD Pipe Failure Data Exchange Project

PDF

Topics: Failure data , Nuclear power stations , Pipes , Service life (Equipment) , Databases , Leakage , Fracture (Materials) , Nuclear power , ASME Standards , Failure

Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs (VERLIFE)

Milan Brumovsky

PVP 2004; 11-14https://doi.org/10.1115/PVP2004-2962

Abstract

View Articletitled, Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs (VERLIFE)

PDF

Topics: Nuclear power stations , Pipes , Pressurized water reactors

Assessment of Remaining Life for Class 1 Piping Components Experiencing Wall Thinning

Rajnish Kumar

PVP 2004; 15-21https://doi.org/10.1115/PVP2004-2963

Abstract

View Articletitled, Assessment of Remaining Life for Class 1 Piping Components Experiencing Wall Thinning

PDF

Topics: Pipes , Remaining life assessment , Nuclear power stations , ASME Boiler and Pressure Vessel Code , Carbon steel , Corrosion , Design , Flow (Dynamics) , Fluids , High pressure (Physics)

French PWR Nuclear Power Plants Steam Generators and Reactor Pressure Vessel Heads Aging Management Criteria and Replacement Strategy

Georges Bezdikian

PVP 2004; 23-31https://doi.org/10.1115/PVP2004-2964

Abstract

View Articletitled, French PWR Nuclear Power Plants Steam Generators and Reactor Pressure Vessel Heads Aging Management Criteria and Replacement Strategy

PDF

Topics: Boilers , Nuclear power stations , Pressurized water reactors , Reactor vessels , Vessels , Alloys , Design , Safety , Security

Aging Management Program: Comparisons Between EDF Methodology and U.S. GALL Report

Claude Faidy

PVP 2004; 33-40https://doi.org/10.1115/PVP2004-2965

Abstract

View Articletitled, Aging Management Program: Comparisons Between EDF Methodology and U.S. GALL Report

PDF

Topics: Damage assessment , Maintenance , Safety

Fatigue Reliability Assessment and Updating With On-Line Nondestructive Inspection for Pressure Vessels

Guohua Chen, Achintya Haldar

PVP 2004; 41-48https://doi.org/10.1115/PVP2004-2966

Abstract

View Articletitled, Fatigue Reliability Assessment and Updating With On-Line Nondestructive Inspection for Pressure Vessels

PDF

Topics: Fatigue , Nondestructive evaluation , Pressure vessels , Reliability , Fracture (Materials) , Inspection , Safety

NRC Review of Time-Limited Aging Analyses for License Renewal Applications

James Medoff, Kenneth C. Chang, Duc Nguyen, Vikram N. Shah

PVP 2004; 49-60https://doi.org/10.1115/PVP2004-2967

Abstract

View Articletitled, NRC Review of Time-Limited Aging Analyses for License Renewal Applications

PDF

Topics: Licensing , Fluence (Radiation measurement) , Neutrons , Embrittlement , Temperature , Boiling water reactors , Ductility , Electrical components , Failure , Fatigue analysis

Time Limited Aging Analyses Requirements for License Renewal for U.S. Nuclear Power Plants

Mansoor H. Sanwarwalla

PVP 2004; 61-68https://doi.org/10.1115/PVP2004-2968

Abstract

View Articletitled, Time Limited Aging Analyses Requirements for License Renewal for U.S. Nuclear Power Plants

PDF

Topics: Licensing , Nuclear power stations , Design , Regulations , Metal fatigue

Certification Program for Assessing the Mechanical Integrity of Pressure Vessel Systems

Chris Alexander, Richard Biel

PVP 2004; 69-76https://doi.org/10.1115/PVP2004-2969

Abstract

View Articletitled, Certification Program for Assessing the Mechanical Integrity of Pressure Vessel Systems

PDF

Topics: Cycles , Design , Design methodology , Failure , Inspection , Offshore platforms , Power stations , Pressure , Pressure vessel systems , Pressure vessels

Neutron Embrittlement of VVER 1000 and 440/213 RPVs: Learning From EC Projects on RPV Integrity

Claude Rieg, Ralf Ahlstrand, Michel Bieth, Luigi Debarberis, Filippo Sevini, Nigel Taylor, Georgy Karzov, Boris Margolin, Yuri Dragunov, Vladimir Piminov, Alexander Kryukov, Yaroslav Shtrombakh

PVP 2004; 77-91https://doi.org/10.1115/PVP2004-2970

Abstract

View Articletitled, Neutron Embrittlement of VVER 1000 and 440/213 RPVs: Learning From EC Projects on RPV Integrity

PDF

Topics: Embrittlement , Neutrons , Surveillance , Design , Annealing , Dosimetry , Fracture toughness , Acceptance criteria , Cladding systems (Building) , Copper

Life Assessment of Components With Underclad Cracks in PWR

Nicolas Verdiere, Pierre Cambefort, Karim Zamoum, Karl Payraudeau, Se´bastien Royer

PVP 2004; 93-96https://doi.org/10.1115/PVP2004-2971

Abstract

View Articletitled, Life Assessment of Components With Underclad Cracks in PWR

PDF

Topics: Fracture (Materials) , Pressurized water reactors , Shells , In-service inspection , Reactor vessels , Boilers , Cladding systems (Building) , Cracking (Materials) , Fracture (Process) , Heat

Lifetime Management of WWER Reactor Pressure Vessels

Milan Brumovsky

PVP 2004; 97-103https://doi.org/10.1115/PVP2004-2972

Abstract

View Articletitled, Lifetime Management of WWER Reactor Pressure Vessels

PDF

Topics: Reactor vessels , Nuclear power stations , Vessels , Neutrons , Surveillance , Cavities , Fluence (Radiation measurement) , Materials properties , Pipes , Safety

License Renewal Program for Entergy’s Fleet of Nuclear Power Plants

Garry G. Young

PVP 2004; 105-111https://doi.org/10.1115/PVP2004-2973

Abstract

View Articletitled, License Renewal Program for Entergy’s Fleet of Nuclear Power Plants

PDF

Topics: Licensing , Nuclear power stations , Teams , Economics , Nuclear industry , Nuclear power

Lifetime Management of EDF PWR Pressure Vessels and Pipings

F. Hedin, J. C. Legendre

PVP 2004; 113-118https://doi.org/10.1115/PVP2004-2974

Abstract

View Articletitled, Lifetime Management of EDF PWR Pressure Vessels and Pipings

PDF

Topics: Pressure vessels , Pressurized water reactors , Maintenance , Safety , Cost benefit analysis , Nondestructive evaluation , Nozzles , Nuclear power stations , Reactor vessels , Stainless steel

Equipment Aging Management and Operational Lifetime Extension at the PAKS Nuclear Power Plant

T. Katona, A. Ja´nosine´ Bi´ro´, S. Ra´tkai, T. Pa´lfi, A. To´th

PVP 2004; 119-125https://doi.org/10.1115/PVP2004-2975

Abstract

View Articletitled, Equipment Aging Management and Operational Lifetime Extension at the PAKS Nuclear Power Plant

PDF

Topics: Nuclear power stations , Licensing , Design , Safety

French R&D Program for RPV Aging Management

H. Churier-Bossennec, D. Moinereau, P. Todeschini, C. Faidy, G. Bezdikian

PVP 2004; 127-132https://doi.org/10.1115/PVP2004-2976

Abstract

View Articletitled, French R&D Program for RPV Aging Management

PDF

Topics: Design , Feedback , Fluence (Radiation measurement) , Fracture toughness , Industrial research , Risk , Rupture , Safety , Surveillance , Transients (Dynamics)

Reactor Pressure Vessel of Tricastin Unit 1 Core Zone Inspection: Comparison of Non-Destructive Examination Results Among Two Core Area Inspections Performed in 1999 and in 2003

Karl Payraudeau, Karim Zamoum, Thierry Pasquier

PVP 2004; 133-136https://doi.org/10.1115/PVP2004-2977

Abstract

View Articletitled, Reactor Pressure Vessel of Tricastin Unit 1 Core Zone Inspection: Comparison of Non-Destructive Examination Results Among Two Core Area Inspections Performed in 1999 and in 2003

PDF

Topics: Inspection , Nondestructive evaluation , Reactor vessels , Dimensions , Cladding systems (Building) , Cycles , In-service inspection , Manufacturing

The Effect of Environments on the Fatigue Life of Pressure Vessel Steel in High-Temperature Water

Hyunchul Cho, In-Sup Kim

PVP 2004; 137-142https://doi.org/10.1115/PVP2004-2978

Abstract

View Articletitled, The Effect of Environments on the Fatigue Life of Pressure Vessel Steel in High-Temperature Water

PDF

Topics: Fatigue life , High temperature , Pressure vessels , Steel , Water , Hardening , Temperature , Stress , Deformation , Hydrogen embrittlement

Procedures on Fracture Toughness Estimation Safety Assessment and Life Extension for In-Service High Pressure Vessels

Guohua Chen, Bonuan Chen

PVP 2004; 143-148https://doi.org/10.1115/PVP2004-2979

Abstract

View Articletitled, Procedures on Fracture Toughness Estimation Safety Assessment and Life Extension for In-Service High Pressure Vessels

PDF

Topics: Fracture toughness , High-pressure vessels , Life extension , Safety , Fracture (Materials) , Temperature , American Petroleum Institute , Brittleness , Crystals , Failure

The French Regulatory Experience and View on Nickel-Base Alloy PWSCC Prevention and Treatment

David Emond, Jacques Reuchet

PVP 2004; 149-164https://doi.org/10.1115/PVP2004-2980

Abstract

View Articletitled, The French Regulatory Experience and View on Nickel-Base Alloy PWSCC Prevention and Treatment

PDF

Topics: Alloys , Nickel , Leakage , Vessels , Boilers , Circuits , Feedback , Inspection , Nondestructive evaluation , Pressurized water reactors

Knowledge Modeling for Asset Management Evaluation

Catherine E. Bauby, Philippe Hai¨k, Emmanuel Remy, Benoiˆt Ricard

PVP 2004; 165-171https://doi.org/10.1115/PVP2004-2981

Abstract

View Articletitled, Knowledge Modeling for Asset Management Evaluation

PDF

Topics: Modeling , Maintenance , Computer software , Economics , Safety

ANO-1 Experiences Using Structural Tools During License Renewal Application

Reza Ahrabli

PVP 2004; 173-177https://doi.org/10.1115/PVP2004-2982

Abstract

View Articletitled, ANO-1 Experiences Using Structural Tools During License Renewal Application

PDF

Topics: Licensing , Regulations , Structural elements (Construction)

Robotics in the Nuclear Environment: Inspection and Repairs Inside the Primary Coolant System

Marcel Tortolano, Jacques Guillet

PVP 2004; 179-187https://doi.org/10.1115/PVP2004-2983

Abstract

View Articletitled, Robotics in the Nuclear Environment: Inspection and Repairs Inside the Primary Coolant System

PDF

Topics: Coolants , Inspection , Maintenance , Robotics , Nuclear power stations , Pressurized water reactors , Optimization , Circuits , Energy generation , Fuels

Application of Hot Hardness Test to the Evaluation of Creep Damage in Cr-Mo-V Turbine Rotor of Fossil Power Plant

Shinsuke Sakai, Satoshi Izumi, Takashi Murakami, Akito Nitta, Junichi Kusumoto, Yu Watanabe

PVP 2004; 189-194https://doi.org/10.1115/PVP2004-2984

Abstract

View Articletitled, Application of Hot Hardness Test to the Evaluation of Creep Damage in Cr-Mo-V Turbine Rotor of Fossil Power Plant

PDF

Topics: Constitutive equations , Creep , Damage , Fossil fuels , Rotors , Turbines

All Years

Piping Service Life Experience in Commercial Nuclear Power Plants: Progress With the OECD Pipe Failure Data Exchange Project

Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs (VERLIFE)

Assessment of Remaining Life for Class 1 Piping Components Experiencing Wall Thinning

French PWR Nuclear Power Plants Steam Generators and Reactor Pressure Vessel Heads Aging Management Criteria and Replacement Strategy

Aging Management Program: Comparisons Between EDF Methodology and U.S. GALL Report

Fatigue Reliability Assessment and Updating With On-Line Nondestructive Inspection for Pressure Vessels

NRC Review of Time-Limited Aging Analyses for License Renewal Applications

Time Limited Aging Analyses Requirements for License Renewal for U.S. Nuclear Power Plants

Certification Program for Assessing the Mechanical Integrity of Pressure Vessel Systems

Neutron Embrittlement of VVER 1000 and 440/213 RPVs: Learning From EC Projects on RPV Integrity

Life Assessment of Components With Underclad Cracks in PWR

Lifetime Management of WWER Reactor Pressure Vessels

License Renewal Program for Entergy’s Fleet of Nuclear Power Plants

Lifetime Management of EDF PWR Pressure Vessels and Pipings

Equipment Aging Management and Operational Lifetime Extension at the PAKS Nuclear Power Plant

French R&D Program for RPV Aging Management

Reactor Pressure Vessel of Tricastin Unit 1 Core Zone Inspection: Comparison of Non-Destructive Examination Results Among Two Core Area Inspections Performed in 1999 and in 2003

The Effect of Environments on the Fatigue Life of Pressure Vessel Steel in High-Temperature Water

Procedures on Fracture Toughness Estimation Safety Assessment and Life Extension for In-Service High Pressure Vessels

The French Regulatory Experience and View on Nickel-Base Alloy PWSCC Prevention and Treatment

Knowledge Modeling for Asset Management Evaluation

ANO-1 Experiences Using Structural Tools During License Renewal Application

Robotics in the Nuclear Environment: Inspection and Repairs Inside the Primary Coolant System

Application of Hot Hardness Test to the Evaluation of Creep Damage in Cr-Mo-V Turbine Rotor of Fossil Power Plant

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