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Journal Articles

Latent Pitfalls in Microstructure-Based Modeling for Thermally Aged 9Cr-1Mo-V Steel (Grade 91)

Weiju Ren

Publisher: ASME

J. Pressure Vessel Technol.

Paper No: PVT-24-1011

https://doi.org/10.1115/1.4066559

Published Online: September 14, 2024

View Article titled, Latent Pitfalls in Microstructure-Based Modeling for Thermally Aged 9Cr-1Mo-V Steel (Grade 91)

Topics: Modeling, Steel, Design, Materials science, Model development, Nuclear reactors, Physics, Reliability, Tensile strength, Testing

Journal Articles

Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading

Bipul Barua, Subhasish Mohanty, Joseph T. Listwan, Saurindranath Majumdar, Krishnamurti Natesan

Publisher: ASME

J. Pressure Vessel Technol. October 2018, 140(5): 051403.

Paper No: PVT-18-1061

https://doi.org/10.1115/1.4040790

Published Online: August 2, 2018

View Article titled, Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading

Topics: Fatigue, Fatigue life, Finite element analysis, Modeling, Stress, Hardening, Nuclear reactors, Stainless steel, Stress analysis (Engineering), Pressurized water reactors

Journal Articles

Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)

Georges Van Goethem

Publisher: ASME

J. Pressure Vessel Technol. August 2011, 133(4): 044001.

https://doi.org/10.1115/1.4002265

Published Online: May 11, 2011

View Article titled, Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)

Topics: Cycles, Design, Fuels, Nuclear fission, Recycling, Safety, Sustainability, Construction, Nuclear power, Heat

Journal Articles

Collapse of Nuclear Reactor SG Tubes Pressurized From Outside: The Influence of Imperfections

Lelio Luzzi, Valentino Di Marcello

Publisher: ASME

J. Pressure Vessel Technol. February 2011, 133(1): 011206.

https://doi.org/10.1115/1.4002769

Published Online: December 23, 2010

View Article titled, Collapse of Nuclear Reactor SG Tubes Pressurized From Outside: The Influence of Imperfections

Topics: Collapse, Hardening, Pressure, Stress, Buckling, External pressure, Nuclear reactors

Journal Articles

Delayed Hydride Cracking Initiation at Notches in Zr-2.5Nb Alloys

Jun Cui, Gordon K. Shek, D. A. Scarth, Zhirui Wang

Publisher: ASME

J. Pressure Vessel Technol. August 2009, 131(4): 041407.

https://doi.org/10.1115/1.3141433

Published Online: July 1, 2009

View Article titled, Delayed Hydride Cracking Initiation at Notches in Zr-2.5Nb Alloys

Topics: Alloys, Cracking (Materials), Cycles, Fracture (Materials), Fracture (Process), Metallography, Pressure, Stress, Zirconium, Creep

Journal Articles

A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers

Weiju Ren, Robert Swindeman

Publisher: ASME

J. Pressure Vessel Technol. August 2009, 131(4): 044002.

https://doi.org/10.1115/1.3121522

Published Online: May 26, 2009

View Article titled, A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers

Topics: Alloys, Creep, Fatigue, Temperature, Fracture (Materials), Stress, Nuclear reactors, Rupture

Journal Articles

A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Marjorie Ann EricksonKirk, Mark T. EricksonKirk, Stan Rosinski, Jack Spanner

Publisher: ASME

J. Pressure Vessel Technol. June 2009, 131(3): 031404.

https://doi.org/10.1115/1.3109987

Published Online: April 17, 2009

View Article titled, A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Topics: Databases, Fracture toughness, Steel, Temperature, Temperature effects, Fittings, Shear (Mechanics), Phase transition temperature, Nuclear reactors

Journal Articles

A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications

Weiju Ren, Robert Swimdeman

Publisher: ASME

J. Pressure Vessel Technol. April 2009, 131(2): 024002.

https://doi.org/10.1115/1.2967885

Published Online: December 30, 2008

View Article titled, A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications

Topics: Alloys, Creep, Fatigue, Fracture (Materials), Nuclear reactors, Temperature, Tensile strength, Indium alloys, Fracture toughness, Very high temperature reactors

Journal Articles

Fluid-Structure Interaction Effects Modeling for the Modal Analysis of a Nuclear Pressure Vessel

Jean-François Sigrist, Daniel Broc, Christian Lainé

Publisher: ASME

J. Pressure Vessel Technol. February 2007, 129(1): 1–6.

https://doi.org/10.1115/1.2389025

Published Online: March 17, 2006

View Article titled, Fluid-Structure Interaction Effects Modeling for the Modal Analysis of a Nuclear Pressure Vessel

Topics: Fluid structure interaction, Fluids, Modal analysis, Modeling, Reactor vessels, Stiffness, Nuclear reactors, Finite element analysis, Pressure

Journal Articles

Guest Editorial

Gerry Slagis

Publisher: ASME

J. Pressure Vessel Technol. February 2004, 126(1): 1.

https://doi.org/10.1115/1.1638790

Published Online: February 26, 2004

View Article titled, Guest Editorial

Topics: Design, Earthquake engineering, Earthquakes, Nuclear engineering computing, Nuclear reactor materials, Nuclear reactor safety, Nuclear reactors, Pressure vessels, Pipes

Journal Articles

Residual Stresses in Steel and Zirconium Weldments

J. H. Root, C. E. Coleman, J. W. Bowden, M. Hayashi

Publisher: ASME

J. Pressure Vessel Technol. May 1997, 119(2): 137–141.

https://doi.org/10.1115/1.2842274

Published Online: May 1, 1997

View Article titled, Residual Stresses in Steel and Zirconium Weldments

Topics: Residual stresses, Steel, Zirconium, Neutron diffraction, Stress, Electron beam welding, Welding, Cathode ray oscilloscopes, Cracking (Materials), Electron beams

Journal Articles

A New Method of Nondestructive Measurement for Assessment of Material Degradation of Aged Reactor Pressure Vessels

K. Ara, N. Ebine, N. Nakajima

Publisher: ASME

J. Pressure Vessel Technol. November 1996, 118(4): 447–453.

https://doi.org/10.1115/1.2842212

Published Online: November 1, 1996

View Article titled, A New Method of Nondestructive Measurement for Assessment of Material Degradation of Aged Reactor Pressure Vessels

Topics: Magnetic fields, Materials degradation, Nuclear reactors, Overlays (Materials engineering), Poles (Building), Pressure vessels, Radiation (Physics), Radiation damage, Reactor vessels, Stainless steel

Journal Articles

Detection and Sizing of Defects in Control Rod Drive Mechanism Penetrations Using Eddy Current and Ultrasonics

G. M. Light, J. L Fisher, R. F. Tennis, J. S. Stolte, G. J. Hendrix

Publisher: ASME

J. Pressure Vessel Technol. August 1996, 118(3): 301–307.

https://doi.org/10.1115/1.2842192

Published Online: August 1, 1996

View Article titled, Detection and Sizing of Defects in Control Rod Drive Mechanism Penetrations Using Eddy Current and Ultrasonics

Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Ultrasonics, Nondestructive evaluation, Probes, Annulus, Flaw detection, Fracture (Materials), Ultrasonic transducers, Coolants

Journal Articles

Alternative Method of RT NDT Determination for Some Reactor Vessel Weld Metals Validated by Fracture Toughness Data

K. K. Yoon

Publisher: ASME

J. Pressure Vessel Technol. November 1995, 117(4): 378–382.

https://doi.org/10.1115/1.2842139

Published Online: November 1, 1995

View Article titled, Alternative Method of RT NDT Determination for Some Reactor Vessel Weld Metals Validated by Fracture Toughness Data

Topics: Fracture toughness, Metals, Reactor vessels, Temperature, Ductility, Weight (Mass), ASME Standards, ASTM International, Embrittlement, Fluence (Radiation measurement)

Journal Articles

Application of Ultrasonics to Nonintrusive Vibration Measurement

M. K. Au-Yang

Publisher: ASME

J. Pressure Vessel Technol. November 1993, 115(4): 415–419.

https://doi.org/10.1115/1.2929550

Published Online: November 1, 1993

View Article titled, Application of Ultrasonics to Nonintrusive Vibration Measurement

Topics: Ultrasonics, Vibration measurement, Valves, Vibration, Accelerometers, Boilers, Disks, Flutter (Aerodynamics), Heat exchangers, Nuclear reactors

Journal Articles

Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

G. L. Stevens, S. Ranganath

Publisher: ASME

J. Pressure Vessel Technol. August 1991, 113(3): 349–357.

https://doi.org/10.1115/1.2928766

Published Online: August 1, 1991

View Article titled, Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

Topics: Fatigue, Life extension, Nuclear reactors, Stress, Computers, Temperature, Boiling water reactors, Monitoring systems, Feedwater, Finite element analysis

Journal Articles

Study on Underclad Cracking in Nuclear Reactor Vessel Steels

T. Horiya, T. Takeda, K. Yamato

Publisher: ASME

J. Pressure Vessel Technol. February 1985, 107(1): 30–35.

https://doi.org/10.1115/1.3264400

Published Online: February 1, 1985

View Article titled, Study on Underclad Cracking in Nuclear Reactor Vessel Steels

Topics: Cracking (Materials), Fracture (Process), Nuclear reactors, Steel, Vessels, Fracture (Materials), Simulation, Rollers

Journal Articles

Efficient Computational Procedures for Long-Time Duration Fluid-Structure Interaction Problems

W. K. Liu, H. G. Chang

Publisher: ASME

J. Pressure Vessel Technol. November 1984, 106(4): 317–322.

https://doi.org/10.1115/1.3264358

Published Online: November 1, 1984

View Article titled, Efficient Computational Procedures for Long-Time Duration Fluid-Structure Interaction Problems

Topics: Fluid structure interaction, Fluids, Algorithms, Fluid pressure, Pipes, Stability, Waves, Computation, Computers, Dams

Journal Articles

Elastic-Plastic Analyses of Surface Flaws in a Reactor Vessel

W. W. Wilkening, H. G. deLorenzi, M. Barishpolsky

Publisher: ASME

J. Pressure Vessel Technol. August 1984, 106(3): 247–254.

https://doi.org/10.1115/1.3264339

Published Online: August 1, 1984

View Article titled, Elastic-Plastic Analyses of Surface Flaws in a Reactor Vessel

Topics: Deformation, Design, Displacement, Elastic analysis, Finite element methods, Fracture (Materials), Nuclear reactors, Plasticity, Pressure, Pressure vessels

Journal Articles

Development of Engineering Codes of Practice for Corrosion Fatigue

P. M. Scott, B. Tomkins, A. J. E. Foreman

Publisher: ASME

J. Pressure Vessel Technol. August 1983, 105(3): 255–262.

https://doi.org/10.1115/1.3264275

Published Online: August 1, 1983

View Article titled, Development of Engineering Codes of Practice for Corrosion Fatigue

Topics: Corrosion, Engineering standards, Fatigue, Design, Fatigue failure, Alloy steel, Carbon, Fracture (Materials), In-service inspection, Inspection

Journal citation

NARROW

Manuscript

Latent Pitfalls in Microstructure-Based Modeling for Thermally Aged 9Cr-1Mo-V Steel (Grade 91)

Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading

Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)

Collapse of Nuclear Reactor SG Tubes Pressurized From Outside: The Influence of Imperfections

Delayed Hydride Cracking Initiation at Notches in Zr-2.5Nb Alloys

A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers

A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications

Fluid-Structure Interaction Effects Modeling for the Modal Analysis of a Nuclear Pressure Vessel

Guest Editorial

Residual Stresses in Steel and Zirconium Weldments

A New Method of Nondestructive Measurement for Assessment of Material Degradation of Aged Reactor Pressure Vessels

Detection and Sizing of Defects in Control Rod Drive Mechanism Penetrations Using Eddy Current and Ultrasonics

Alternative Method of RT NDT Determination for Some Reactor Vessel Weld Metals Validated by Fracture Toughness Data

Application of Ultrasonics to Nonintrusive Vibration Measurement

Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

Study on Underclad Cracking in Nuclear Reactor Vessel Steels

Efficient Computational Procedures for Long-Time Duration Fluid-Structure Interaction Problems

Elastic-Plastic Analyses of Surface Flaws in a Reactor Vessel

Development of Engineering Codes of Practice for Corrosion Fatigue

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