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1.

図書

図書
sponsored by the Pressure Vessels and Piping Division, ASME ; edited by W.H. Bamford ; contributing editors, M.J. Cohn ... [etal.]
出版情報: New York, N.Y. : American Society of Mechanical Engineers, c1996  vi, 261 p. ; 28 cm
シリーズ名: PVP ; vol. 335
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2.

図書

図書
presented at the 1991 Pressure Vessels and Piping Conference, San Diego, California, June 23-27, 1991 ; sponsored by the Pressure Vessels and Piping Division, ASME ; edited by W.H. Bamford ; contributing editors, T.A. Meyer ... [et al.]
出版情報: New York, N.Y. : American Society of Mechanical Engineers, c1991  vi, 201 p. ; 28 cm
シリーズ名: PVP ; vol. 215
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3.

図書

図書
presented at the 1991 Pressure Vessels and Piping Conference, San Diego, California, June 23-27, 1991 ; sponsored by the Pressure Vessels and Piping Division, ASME ; edited by W.H. bamford ; contributing editors, R.C. Cipolla, C.E. Jaske
出版情報: New York, N.Y. : American Society of Mechanical Engineers, c1991  v, 123 p. ; 28 cm
シリーズ名: PVP ; vol. 221
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4.

図書

図書
presented at the 1992 Pressure Vessels and Piping Conference, New Orleans, Louisiana, June 21-25, 1992 ; sponsored by the Pressure Vessels and Piping Division, ASME ; principal editor, W.H. Bamford ; contributing editors, H. Mehta ... [et al.]
出版情報: New York, N.Y. : American Society of Mechanical Engineers, c1992  v, 133 p. ; 28 cm
シリーズ名: PVP ; vol. 241
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5.

図書

図書
sponsored by the Pressure Vessels and Piping Division, ASME ; edited by W.H. Bamford
出版情報: New York, N.Y. (345 E. 47th St., New York 10017) : American Society of Mechanical Engineers, c1993  vi, 345 p. ; 28 cm
シリーズ名: PVP ; vol. 261
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6.

図書

図書
sponsored by the Pressure Vessels and Piping Division, ASME, ; principal editor, J. Pan ; contibuting editors, M. J. Cohn, W.H. Bamford, D. P. Lidbury
出版情報: New York : American Society of Mechanical Engineers, c1999  vi, 319 p. ; 28 cm
シリーズ名: PVP ; v. 392
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目次情報: 続きを見る
Service Experience in Fossil Fuel Plants
Introduction / Marvin J. Cohn
Failure Analysis and Life Assessment Studies for Boiler Tubes / F. V. Ellis ; Sebastian Tordonato
Comparison of Flow-Accelerated Corrosion Prediction and Field Measurement Results
Correlation Between Human and Material Shocks in Symptom-Based Emergency Procedures / Gueorgui I. Petkov ; Pavlin P. Groudev
Effects of Crude Oil on the Thermo-Mechanical Properties of High Density Polyethylene / Abdennour C. Seibi
A Review of High Temperature Performance Trends and Design Rules for 2 1/4Cr-1Mo Steel Weldments / Robert W. Warke ; R. Viswanathan
Creep-Rupture Properties of 2-1/4Cr-1Mo Steel Plate Material
Experience With High Temperature Injection Steam Valves in a Supercritical Coal Fired Power Plant / S. M. French
Main Steam Link Failure: Kansas City Power and Light Hawthorn Unit 5 / Francis E. Moore, Jr. ; Glenn N. Beckerdite
Service Experience in Operating Nuclear Plants
Evaluation of Fatigue-Induced Field Failures of Socket-Welded Joints in Small Bore Piping / Daniel N. Hopkins ; Daniel J. Benac
Integrity Assessment of Part Length CRDM Housings in Operating Westinghouse PWRs / W. H. Bamford ; N. B. Closky ; G. V. Rao ; R. K. Cooper ; J. G. Johnston III ; T. F. Huminski
A Review of Nuclear Piping Failures and Their Use in Establishing the Reliability of Piping Systems / Spencer H. Bush
Understanding Section XI Examination Coverage Requirements / Owen F. Hedden
Inherent Fracture Margins in BWR Pressure Vessels and Justification for Reduced Inspection of Vessel Welds / Sampath Ranganath ; Larry D. Steinert ; Robert G. Carter
Risk Informed Assessment of Inservice Inspection of Reactor Pressure Vessel Welds in Boiling Water Reactors / Barry J. Elliot ; Keith R. Wichman ; Clarence E. Carpenter
Use of Voluntary Industry Initiatives in Place of Regulatory Actions / Robert A. Hermann ; Edmund J. Sullivan
ASME Section XI Evaluation Methods and Acceptance Criteria for Analytical Evaluation of Wall Thinning Due to Flow Accelerated Corrosion (FAC) / A. Deardorff ; L. Goyette ; P. Krishnaswamy ; M. Kupinski
Baffle Bolt Inspection and Replacement at Farley Unit #1 / D. R. Forsyth ; J. A. Klimek ; J. T. Polidora ; D. M. Trombola ; A. M. Dobler ; A. E. Jones
Development and User Experience of New Methodologies of Structural Integrity Assessment
Developments in European Defect Assessment Procedures / David P. Lidbury ; John K. Sharples ; Anthony R. Dowling ; Robert A. Ainsworth
Experimental Validation of R6 Treatment of Residual Stresses / Christine C. France
Analysis of Benchmark PTS Problem: Comparison of R6 and 3D-Finite Element Results / Andrew H. Sherry ; Tom Richardson ; Bob Sillitoe ; Fraser Trusty
Constraint Based Failure Assessment Diagrams for Primary and Secondary Loading / J. W. Hancock
Application of Local Approach Modelling of Constraint Contributions to the Ductile to Brittle Transition / David W. Beardsmore ; Mark Wilkes ; Peter J. Bramah ; David C. Connors ; Antony B. Parsons
Probabilistic Assessment of the NESC-1 Spinning Cylinder Experiment / John S. Schofield ; David I. Swan
Equipment Assessment
Utilizing On-Stream Inspection Techniques in the Petroleum/Petrochemical Industry in Lieu of Internal and Turnaround Inspections / John Reynolds ; Mark Bell
Ultrasonic Detection, Characterization, and Quantification of Localized High Temperature Hydrogen Attack in Weld and Heat-Affected Zone / W. David Wang
Student Papers
Application of Computer Aided System for Statistical Analysis of Experimental Data / Michael D. Smith ; Jerry K. Keska
Using Computer Aided Speckle Interferometry to Measure Pressure Effects on the Heart / Glenn R. Gaudette ; Joseph Todaro ; Fu-Pen Chiang ; Irvin B. Krukenkamp
Author Index
Service Experience in Fossil Fuel Plants
Introduction / Marvin J. Cohn
Failure Analysis and Life Assessment Studies for Boiler Tubes / F. V. Ellis ; Sebastian Tordonato
7.

図書

図書
ASME Pressure Vessels and Piping Conference ; American Society of Mechanical Engineers. Pressure Vessels and Piping Division ; Warke, R. W. (Robert W.) ; Bamford, W. H. (Warren H.) ; Rodgers, Douglas ; Cohn, M. J. ; Dong, P. (Pingsha)
出版情報: New York, N.Y. : American Society of Mechanical Engineers, c2001  v, 147 p. ; 28 cm
シリーズ名: PVP ; v. 427
所蔵情報: loading…
目次情報: 続きを見る
Service Experience in Operating Nuclear Plants
A Fracture Mechanics Evaluation of Observed Cracking in a Recirculation Pump Shaft / H. S. Mehta
An Analysis of Thinning Status for Feeder Pipes in Korean CANDU Plants / S. Jegarl ; H.-S. Chung ; S.-H. Lee
Flaws in Vessel Cladding and Their Potential Contributions to Vessel Failure Probabilities / F. A. Simonen ; S. R. Doctor ; G. J. Schuster ; D. A. Jackson ; L. Abramson
Development of the Technical Basis for Plant Startup for the V. C. Summer Nuclear Plant / G. Moffat ; W. H. Bamford ; K. R. Hsu ; L. Tunon-Sanjur ; D. Seeger ; D. C. Bhomick
Service Experience in Fossil Fuel Plants
Introduction / Marvin J. Cohn
Effect of Operation Temperature on Life Consumption for 1 1/4Cr-1/2Mo-Si and 2 1/4Cr-1Mo Materials / M. J. Cohn
Root Cause Failure Assessment of the Waterwall Tubing at Newington Station, Unit 1 / F. V. Ellis ; S. Tordonato ; M. R. Latour
Weld Residual Stresses and Fracture
Numerical Investigations of the Residual Stresses for the Fracture Assessment of a BWR Pump Nozzle / Pingsha Dong ; Frederick W. Brust ; E. Keim ; P. Palagyi
Stress Intensity Factor Solutions for Welded Joints Subjected to Weld Residual Stresses / P. Dong ; J. K. Hong
A New Mesh-Insensitive Procedure for Characterizing Stress Concentration at Welds / Z. Cao
Residual Stress and Deformation of Narrow Groove Welding / R. Sumiya ; M. Asano
Fabrication and Performance
Influence of Weld Defects on Very Low Cycle Fatigue Properties of Welded Joints / Robert W. Warke ; Y. Kayamori ; A. Seto ; T. Masuda ; S. Machida ; C. Miki
Specimen Size Effect on the Creep-Fatigue Life of a Weld Joint in 2.25Cr-1Mo Steel / T. Ogata
Creep-Rupture Properties of Modified 9Cr-1Mo Weld Metal / W. H. Zielke
Influence of Gas Type on the Mechanical Properties of Heat Affected Zone During Oxyfuel Cutting of Carbon Steel / P. Munoz-Escalona ; M. C. Payares ; T. Ascanio
Empirical Model of Grinding for the Prediction of Roughness on Stainless Steels / Z. Cassier ; O. Zurita
Author Index
Service Experience in Operating Nuclear Plants
A Fracture Mechanics Evaluation of Observed Cracking in a Recirculation Pump Shaft / H. S. Mehta
An Analysis of Thinning Status for Feeder Pipes in Korean CANDU Plants / S. Jegarl ; H.-S. Chung ; S.-H. Lee
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