Topics: Steel , Neutrons , Ductile-brittle transition , Economics , Embrittlement , Irradiation (Radiation exposure) , Reactor vessels , Regression analysis , Surveillance , Temperature

Neutron Embrittlement Aging Management of Nuclear Reactor Pressure Vessels

William L. Server

PVP 2003; 17-28https://doi.org/10.1115/PVP2003-2150

Abstract

View Articletitled, Neutron Embrittlement Aging Management of Nuclear Reactor Pressure Vessels

PDF

Topics: Embrittlement , Neutrons , Nuclear reactors , Pressure vessels , Fracture toughness , ASTM International , Reactor vessels , Phase transition temperature , Surveillance , Vessels

French RPV PTS Assessment: An Overview of EDF Research and Development in Progress on Thermalhydraulic, Materials and Mechanical Aspects

Dominique Moinereau, Jean-Michel Frund, Henriette Churier-Bossennec, Georges Bezdikian, Alain Martin

PVP 2003; 29-50https://doi.org/10.1115/PVP2003-2151

Abstract

View Articletitled, French RPV PTS Assessment: An Overview of EDF Research and Development in Progress on Thermalhydraulic, Materials and Mechanical Aspects

PDF

Topics: Computation , Computational fluid dynamics , Fracture (Materials) , Industrial research , Materials properties , Reactor vessels , Stress , Thermal shock , Transients (Dynamics) , Vessels

French Four-Loop PWR 1300 MWe Reactor Pressure Vessel: First Results for Integrity Assessment and Life Manangement

Georges Bezdikian, Franc¸oise Ternon-Morin, Henriette Churier-Bossennec, Dominique Moinereau, Alain Martin

PVP 2003; 51-62https://doi.org/10.1115/PVP2003-2152

Abstract

View Articletitled, French Four-Loop PWR 1300 MWe Reactor Pressure Vessel: First Results for Integrity Assessment and Life Manangement

PDF

Topics: Pressurized water reactors , Reactor vessels , Fluence (Radiation measurement) , Radiation (Physics) , Vessels , Brittle fracture , Cladding systems (Building) , Inspection , Nondestructive evaluation , Nuclear power stations

A Life Extension Perspective for a CANDU-6 NPP: Gentilly-2 Plant Condition Assessments

Marc Aubray

PVP 2003; 63-69https://doi.org/10.1115/PVP2003-2153

Abstract

View Articletitled, A Life Extension Perspective for a CANDU-6 NPP: Gentilly-2 Plant Condition Assessments

PDF

Topics: Life extension , Nuclear power stations , Design , Governments , Licensing , Pressure , Safety

Integrated Plant Life Cycle Management: The IAEA Contribution

Ki-Sig Kang, Claude Russell Clark, Poong Eil Juhn

PVP 2003; 71-78https://doi.org/10.1115/PVP2003-2154

Abstract

View Articletitled, Integrated Plant Life Cycle Management: The IAEA Contribution

PDF

Topics: Life cycle management , Nuclear power stations , Nuclear power , Cycles , Maintenance , Nuclear decommissioning , Optimization , Service life (Equipment) , Economic analysis , Instrumentation

Asset Management Evaluation Methods: The EDF Perspective

Catherine E. Bauby, Vale´ry E. Just, Caroline Garreau

PVP 2003; 79-85https://doi.org/10.1115/PVP2003-2155

Abstract

View Articletitled, Asset Management Evaluation Methods: The EDF Perspective

PDF

Topics: Economic analysis , Economics , Evaluation methods , Maintenance , Pressurized water reactors , Reliability , Safety , Uncertainty

Modeling Swirl Penetration and Thermal Cycling in Un-Isolable Branch Lines of PWR Plants

Jeffrey D. Keller, Alan J. Bilanin, Stan T. Rosinski

PVP 2003; 87-94https://doi.org/10.1115/PVP2003-2156

Abstract

View Articletitled, Modeling Swirl Penetration and Thermal Cycling in Un-Isolable Branch Lines of PWR Plants

PDF

Topics: Modeling , Pressurized water reactors , Pipes , Boundary-value problems , Coolants , Fatigue cracks , Fluids , Industrial research , Model development , Reynolds number

Data Analysis for RPV Life Management Studies of Temperature Measurements From Monitoring of Safety Injection Fluid in Spent Fuel Pit Cooling and Treatment System Storage Tank

Dominique Lagrange, Vincent Venturini, Georges Bezdikian, Jacques Salaun

PVP 2003; 95-99https://doi.org/10.1115/PVP2003-2157

Abstract

View Articletitled, Data Analysis for RPV Life Management Studies of Temperature Measurements From Monitoring of Safety Injection Fluid in Spent Fuel Pit Cooling and Treatment System Storage Tank

PDF

Topics: Cooling , Fluids , Safety , Spent nuclear fuels , Storage tanks , Temperature measurement , Temperature , Approximation , Low temperature , Nuclear power stations

The European Network AMES for Reactor Component Ageing in the 6th EURATOM Framework Programme

F. Sevini, L. Debarberis, R. Gerard, M. Brumovsky

PVP 2003; 101-105https://doi.org/10.1115/PVP2003-2158

Abstract

View Articletitled, The European Network AMES for Reactor Component Ageing in the 6th EURATOM Framework Programme

PDF

Topics: Annealing , Embrittlement , Nuclear power stations , Nuclear reactors , Performance , Steel

A Help for Lifetime Management: Defect Characterisation Through Signal Processing of Ultrasonic Data

S. Gautier, L. Cha˜tellier

PVP 2003; 107-112https://doi.org/10.1115/PVP2003-2159

Abstract

View Articletitled, A Help for Lifetime Management: Defect Characterisation Through Signal Processing of Ultrasonic Data

PDF

Topics: Signal processing , Echoes , Inspection , Nondestructive evaluation , Corners (Structural elements) , Degrees of freedom , Diffraction , Flight , In-service inspection , Optical mirrors

Mechanical Stress Improvement Process (MSIP) Used to Prevent and Mitigate Primary Water Stress Corrosion Cracking (PWSCC) in Reactor Vessel Piping at V.C. Summer

E. A. Ray, K. Weir, C. Rice, T. Damico

PVP 2003; 113-121https://doi.org/10.1115/PVP2003-2160

Abstract

View Articletitled, Mechanical Stress Improvement Process (MSIP) Used to Prevent and Mitigate Primary Water Stress Corrosion Cracking (PWSCC) in Reactor Vessel Piping at V.C. Summer

PDF

Topics: Pipes , Reactor vessels , Stress , Stress corrosion cracking , Water , Nozzles , Boiling water reactors , Leakage , Maintenance , Pressurized water reactors

A Decision Advisor to Manage the Implications of Alloy 600 Issues

R. K. Perdue, C. W. Mycoff, J. Woodcock, T. A. Meyer, R. Llovet

PVP 2003; 123-129https://doi.org/10.1115/PVP2003-2161

Abstract

View Articletitled, A Decision Advisor to Manage the Implications of Alloy 600 Issues

PDF

Topics: Alloys , Inspection , Crack propagation , Fracture (Materials) , Maintenance , Computer software , Decision making , Energy generation , Framing (Construction) , Leakage

Managing the Aging of Critical Components of Nuclear Power Plants

G. Gary Elder, Ricardo Llovet, Theodore A. Meyer, Edward Terek

PVP 2003; 131-137https://doi.org/10.1115/PVP2003-2162

Abstract

View Articletitled, Managing the Aging of Critical Components of Nuclear Power Plants

PDF

Topics: Nuclear power stations , Power stations , Maintenance , Failure mechanisms , Inspection , Reliability

Implicit Fatigue Design of Piping Systems for License Renewal of B31.1 Plants

K. C. Chang

PVP 2003; 139-146https://doi.org/10.1115/PVP2003-2163

Abstract

View Articletitled, Implicit Fatigue Design of Piping Systems for License Renewal of B31.1 Plants

PDF

Topics: Fatigue design , Licensing , Piping systems , Fatigue analysis , Fatigue , Pipes , Stress , Cycles , Fatigue damage , Nuclear power stations

Effective Approaches for Managing Aging Effects in BWR Reactor Coolant System Components for License Renewal

Barry J. Elliot, Vikram N. Shah, Yung Y. Liu

PVP 2003; 147-153https://doi.org/10.1115/PVP2003-2164

Abstract

View Articletitled, Effective Approaches for Managing Aging Effects in BWR Reactor Coolant System Components for License Renewal

PDF

Topics: Boiling water reactors , Licensing , Nuclear reactor coolants , Cracking (Materials) , Fracture (Process) , Irradiation (Radiation exposure) , Pipes , Pressure , Stress corrosion cracking , Cycles

License Renewal in the U.S. and Plant Life Management (PLIM)

Garry G. Young, Mark A. Rinckel

PVP 2003; 155-159https://doi.org/10.1115/PVP2003-2165

Abstract

View Articletitled, License Renewal in the U.S. and Plant Life Management (PLIM)

PDF

Topics: Licensing , Nuclear power stations , Economics , Nuclear industry , Nuclear reactors , Reactor vessels , Safety , Service life (Equipment)

Managing Aging Effects of the Passive Functions of Pressure Retaining Items

Mansoor H. Sanwarwalla

PVP 2003; 161-168https://doi.org/10.1115/PVP2003-2166

Abstract

View Articletitled, Managing Aging Effects of the Passive Functions of Pressure Retaining Items

PDF

Topics: Corrosion , Design , Embrittlement , Erosion , Fatigue , Heat exchangers , High cycle fatigue , HVAC equipment , Life extension , Low cycle fatigue

Significant Corrosion of the Davis-Besse Nuclear Reactor Pressure Vessel Head

Theodore A. Lang

PVP 2003; 169-176https://doi.org/10.1115/PVP2003-2167

Abstract

View Articletitled, Significant Corrosion of the Davis-Besse Nuclear Reactor Pressure Vessel Head

PDF

Topics: Corrosion , Nuclear reactors , Pressure vessels , Nozzles , Damage , Leakage , Alloy steel , Fracture (Materials) , Inspection , Reactor vessels

Effects of Flow Accelerated Corrosion on Piping Steady-State Vibration Evaluations

Brian J. Voll

PVP 2003; 177https://doi.org/10.1115/PVP2003-2168

Abstract

View Articletitled, Effects of Flow Accelerated Corrosion on Piping Steady-State Vibration Evaluations

PDF

Topics: Corrosion , Flow (Dynamics) , Pipes , Steady state , Vibration , Power uprate , Accounting , Failure , Nuclear power stations , Piping systems

A Modified Technique for Crack Formation on Nuclear Steam Generator Tubing

T. H. Lee, Y. J. Oh, I. S. Hwang, H. S. Chung, J. Y. Park

PVP 2003; 179-183https://doi.org/10.1115/PVP2003-2169

Abstract

View Articletitled, A Modified Technique for Crack Formation on Nuclear Steam Generator Tubing

PDF

Topics: Fracture (Materials) , Nuclear reactor steam generators , Tubing , Pressurized water reactors , Alloys , Boilers , Deformation , Eddies (Fluid dynamics) , Eddy currents (Electricity) , Finite element analysis

The Sensitivity of Counterweighted Swing Check Valve Performance to Counterweight Location

L. I. Ezekoye

PVP 2003; 187-192https://doi.org/10.1115/PVP2003-2170

Abstract

View Articletitled, The Sensitivity of Counterweighted Swing Check Valve Performance to Counterweight Location

PDF

Topics: Valves , Flow (Dynamics) , Design , Water hammer

Fitness-for-Service of Pressure Relieving Systems

W. E. Short, II

PVP 2003; 193-201https://doi.org/10.1115/PVP2003-2171

Abstract

View Articletitled, Fitness-for-Service of Pressure Relieving Systems

PDF

Topics: Fitness-for-service , Pressure , Design , Safety , Engineering standards , Failure , Hardware , Pipes , Plant personnel , Pressure vessels

An Investigation on Mechanical Energy Supply in Rotating Flow Passage of Centrifugal Pump

Takaharu Tanaka

PVP 2003; 203https://doi.org/10.1115/PVP2003-2172

Abstract

View Articletitled, An Investigation on Mechanical Energy Supply in Rotating Flow Passage of Centrifugal Pump

PDF

Topics: Centrifugal pumps , Flow (Dynamics) , Pumps , Blades , Design methodology , Energy transformation , Impellers , Internal flow , Rotation , Turbomachinery

The Effect of Piping System Non-Linearity on the Unstable Growth of a Circumferential Through-Wall Crack in a Pipe

E. Smith

PVP 2003; 205-208https://doi.org/10.1115/PVP2003-2173

Abstract

View Articletitled, The Effect of Piping System Non-Linearity on the Unstable Growth of a Circumferential Through-Wall Crack in a Pipe

PDF

Topics: Fracture (Materials) , Pipes , Piping systems , Deformation , Geometry , Materials properties , Fatigue cracks , Rupture , Safety , Steel

TOFD Automatic Ultrasonic Testing for Condition Monitoring of Coke Drums

Jorge A. Penso, Robert Owen, Masaaki Oka

PVP 2003; 209-216https://doi.org/10.1115/PVP2003-2174

Abstract

View Articletitled, TOFD Automatic Ultrasonic Testing for Condition Monitoring of Coke Drums

PDF

Topics: Coke , Condition monitoring , Diffraction , Flight , Ultrasonic testing

Study and Application of Health Monitoring by Fiber Optic Sensors in Civil Engineering

Hong-Nan Li, Dong-Sheng Li, Su-Yan Wang

PVP 2003; 217-224https://doi.org/10.1115/PVP2003-2175

Abstract

View Articletitled, Study and Application of Health Monitoring by Fiber Optic Sensors in Civil Engineering

PDF

Topics: Civil engineering , Fiber optic sensors , Damage , Fibers , Leakage , Packing (Shipments) , Packings (Cushioning) , Pipelines , Structural health monitoring , Structures

Identifying Rogating Blades Vibration From the Shaft Torsional Vibration Signals

B. O. Al-Bedoor, Y. Al-Nassar, S. A. Adewusi, L. Ghoutti

PVP 2003; 225-231https://doi.org/10.1115/PVP2003-2176

Abstract

View Articletitled, Identifying Rogating Blades Vibration From the Shaft Torsional Vibration Signals

PDF

Topics: Blades , Signals , Vibration , Vibration measurement , Disks , Rotating blades , Rotor vibration , Rotors , Steady state , Strain gages

Finite Element Study on Piezoelectric Sensors for Blade Vibration Measurements

M. Sunar, B. O. Al-Bedoor

PVP 2003; 233-241https://doi.org/10.1115/PVP2003-2177

Abstract

View Articletitled, Finite Element Study on Piezoelectric Sensors for Blade Vibration Measurements

PDF

Topics: Blades , Finite element analysis , Sensors , Vibration measurement , Vibration , Cantilever beams , Disks , Finite element methods , Rotation , Turbomachinery

Effect of Fluid Mass on Non-Linear Natural Frequencies of a Rotating Beam

Ahmad A. Al-Qaisia

PVP 2003; 243-249https://doi.org/10.1115/PVP2003-2178

Abstract

View Articletitled, Effect of Fluid Mass on Non-Linear Natural Frequencies of a Rotating Beam

PDF

Topics: Fluids , Rotating beams , Nonlinear equations , Stability

Finite Element Modeling of Blade-Rotor System in Turbomachinery

Y. N. Al-Nassar

PVP 2003; 251-254https://doi.org/10.1115/PVP2003-2179

Abstract

View Articletitled, Finite Element Modeling of Blade-Rotor System in Turbomachinery

PDF

Topics: Blades , Finite element analysis , Modeling , Rotors , Turbomachinery , Bearings , Disks , Modal analysis , Vibration

All Years

French Procedure for Ageing Management Program of Safety Components

Development of Prediction Equations on Charpy Upper Shelf Energy for Japanese RPV Steels

Neutron Embrittlement Aging Management of Nuclear Reactor Pressure Vessels

French RPV PTS Assessment: An Overview of EDF Research and Development in Progress on Thermalhydraulic, Materials and Mechanical Aspects

French Four-Loop PWR 1300 MWe Reactor Pressure Vessel: First Results for Integrity Assessment and Life Manangement

A Life Extension Perspective for a CANDU-6 NPP: Gentilly-2 Plant Condition Assessments

Integrated Plant Life Cycle Management: The IAEA Contribution

Asset Management Evaluation Methods: The EDF Perspective

Modeling Swirl Penetration and Thermal Cycling in Un-Isolable Branch Lines of PWR Plants

Data Analysis for RPV Life Management Studies of Temperature Measurements From Monitoring of Safety Injection Fluid in Spent Fuel Pit Cooling and Treatment System Storage Tank

The European Network AMES for Reactor Component Ageing in the 6th EURATOM Framework Programme

A Help for Lifetime Management: Defect Characterisation Through Signal Processing of Ultrasonic Data

Mechanical Stress Improvement Process (MSIP) Used to Prevent and Mitigate Primary Water Stress Corrosion Cracking (PWSCC) in Reactor Vessel Piping at V.C. Summer

A Decision Advisor to Manage the Implications of Alloy 600 Issues

Managing the Aging of Critical Components of Nuclear Power Plants

Implicit Fatigue Design of Piping Systems for License Renewal of B31.1 Plants

Effective Approaches for Managing Aging Effects in BWR Reactor Coolant System Components for License Renewal

License Renewal in the U.S. and Plant Life Management (PLIM)

Managing Aging Effects of the Passive Functions of Pressure Retaining Items

Significant Corrosion of the Davis-Besse Nuclear Reactor Pressure Vessel Head

Effects of Flow Accelerated Corrosion on Piping Steady-State Vibration Evaluations

A Modified Technique for Crack Formation on Nuclear Steam Generator Tubing

The Sensitivity of Counterweighted Swing Check Valve Performance to Counterweight Location

Fitness-for-Service of Pressure Relieving Systems

An Investigation on Mechanical Energy Supply in Rotating Flow Passage of Centrifugal Pump

The Effect of Piping System Non-Linearity on the Unstable Growth of a Circumferential Through-Wall Crack in a Pipe

TOFD Automatic Ultrasonic Testing for Condition Monitoring of Coke Drums

Study and Application of Health Monitoring by Fiber Optic Sensors in Civil Engineering

Identifying Rogating Blades Vibration From the Shaft Torsional Vibration Signals

Finite Element Study on Piezoelectric Sensors for Blade Vibration Measurements

Effect of Fluid Mass on Non-Linear Natural Frequencies of a Rotating Beam

Finite Element Modeling of Blade-Rotor System in Turbomachinery

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