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Journal Articles

Nuclear Power in Europe 2012

Luc H. Geraets, Ir. Yves A. Crommelynck

Publisher: ASME

J. Pressure Vessel Technol. December 2012, 134(6): 064001.

https://doi.org/10.1115/1.4007979

Published Online: October 25, 2012

View Article titled, Nuclear Power in Europe 2012

Topics: Nuclear power, Nuclear power stations, Earthquakes, Safety, Stress, Fukushima nuclear disaster, Japan, 2011, Nuclear decommissioning, Construction

Journal Articles

Effective Materials Property Information Management for the 21st Century

Weiju Ren, David Cebon, Steven M. Arnold

Publisher: ASME

J. Pressure Vessel Technol. August 2011, 133(4): 044002.

https://doi.org/10.1115/1.4002925

Published Online: May 17, 2011

View Article titled, Effective Materials Property Information Management for the 21st Century

Topics: Databases, Design, Materials properties, Computer software, Computer-aided engineering

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

Plant Life Management Models: A Comparison With Analysis of Impact on Both Safety and Nonsafety Issues

Paolo Contri, Bernhard Elsing

Publisher: ASME

J. Pressure Vessel Technol. June 2011, 133(3): 034001.

https://doi.org/10.1115/1.4002553

Published Online: April 6, 2011

View Article titled, Plant Life Management Models: A Comparison With Analysis of Impact on Both Safety and Nonsafety Issues

Topics: Maintenance, Nuclear power stations, Safety, Decision making

Journal Articles

Mechanics of Pipes Conveying Fluids—Part II: Applications and Fluidelastic Problems

R. A. Ibrahim

Publisher: ASME

J. Pressure Vessel Technol. April 2011, 133(2): 024001.

https://doi.org/10.1115/1.4001270

Published Online: February 28, 2011

View Article titled, Mechanics of Pipes Conveying Fluids—Part II: Applications and Fluidelastic Problems

Topics: Cross-flow, Flow (Dynamics), Fluids, Heat exchangers, Pipes, Stability, Vibration, Wear, Water, Boilers

Journal Articles

Damping of Heat Exchanger Tubes in Liquids: Review and Design Guidelines

M. J. Pettigrew, R. J. Rogers, F. Axisa

Publisher: ASME

J. Pressure Vessel Technol. February 2011, 133(1): 014002.

https://doi.org/10.1115/1.4000711

Published Online: January 21, 2011

View Article titled, Damping of Heat Exchanger Tubes in Liquids: Review and Design Guidelines

Topics: Damping, Heat exchangers, Friction

Journal Articles

A Survey of Fitness-for-Service Trends in Industry

C. M. Holtam, D. P. Baxter, I. A. Ashcroft, R. C. Thomson

Publisher: ASME

J. Pressure Vessel Technol. February 2011, 133(1): 014001.

https://doi.org/10.1115/1.4001946

Published Online: January 20, 2011

View Article titled, A Survey of Fitness-for-Service Trends in Industry

Topics: Fitness-for-service

Journal Articles

Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views

Randy K. Nanstad, B. Richard Bass, John G. Merkle, Claud E. Pugh, Thomas M. Rosseel, Mikhail A. Sokolov

Publisher: ASME

J. Pressure Vessel Technol. December 2010, 132(6): 064001.

https://doi.org/10.1115/1.4001425

Published Online: October 14, 2010

View Article titled, Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views

Topics: Fracture (Materials), Fracture toughness, Irradiation (Radiation exposure), Steel, Temperature, Thermal shock, Vessels, Fracture (Process), Embrittlement, Neutrons

Journal Articles

Overview of Mechanics of Pipes Conveying Fluids—Part I: Fundamental Studies

R. A. Ibrahim

Publisher: ASME

J. Pressure Vessel Technol. June 2010, 132(3): 034001.

https://doi.org/10.1115/1.4001271

Published Online: May 18, 2010

View Article titled, Overview of Mechanics of Pipes Conveying Fluids—Part I: Fundamental Studies

Topics: Flow (Dynamics), Fluids, Pipes, Stability

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

The Fabulous Nuclear Odyssey of Belgium

Luc H. Geraets, Ph.D.

Publisher: ASME

J. Pressure Vessel Technol. June 2009, 131(3): 034001.

https://doi.org/10.1115/1.3106035

Published Online: April 6, 2009

View Article titled, The Fabulous Nuclear Odyssey of Belgium

Topics: Accidents, Design, Energy generation, Fuels, Nuclear fuel cycle, Nuclear power stations, Reactor vessels, Safety, Construction, Governments

Journal Articles

Proposed New Fatigue Design Curves for Carbon and Low-Alloy Steels in High Temperature Water

William J. O’Donnell, William John O’Donnell, Thomas P. O’Donnell

Publisher: ASME

J. Pressure Vessel Technol. April 2009, 131(2): 024003.

https://doi.org/10.1115/1.3006896

Published Online: January 27, 2009

View Article titled, Proposed New Fatigue Design Curves for Carbon and Low-Alloy Steels in High Temperature Water

Topics: Alloys, ASME Standards, Carbon, Fatigue, Fatigue design, Fatigue strength, Fracture (Materials), Steel, Water, Fatigue cracks

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

Applicable Contact Force Models for the Discrete Element Method: The Single Particle Perspective

H. Kruggel-Emden, S. Wirtz, V. Scherer

Publisher: ASME

J. Pressure Vessel Technol. April 2009, 131(2): 024001.

https://doi.org/10.1115/1.3040682

Published Online: December 11, 2008

View Article titled, Applicable Contact Force Models for the Discrete Element Method: The Single Particle Perspective

Topics: Collisions (Physics), Discrete element methods, Particulate matter, Simulation, Springs, Displacement, Stiffness, Granular materials

Journal Articles

The European Creep Collaborative Committee (ECCC) Approach to Creep Data Assessment

Stuart Holdsworth

Publisher: ASME

J. Pressure Vessel Technol. May 2008, 130(2): 024001.

https://doi.org/10.1115/1.2894296

Published Online: March 25, 2008

View Article titled, The European Creep Collaborative Committee (ECCC) Approach to Creep Data Assessment

Topics: Creep, Rupture, Stress, Relaxation (Physics)

Journal citation

NARROW

Nuclear Power in Europe 2012

Effective Materials Property Information Management for the 21st Century

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

Plant Life Management Models: A Comparison With Analysis of Impact on Both Safety and Nonsafety Issues

Mechanics of Pipes Conveying Fluids—Part II: Applications and Fluidelastic Problems

Damping of Heat Exchanger Tubes in Liquids: Review and Design Guidelines

A Survey of Fitness-for-Service Trends in Industry

Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views

Overview of Mechanics of Pipes Conveying Fluids—Part I: Fundamental Studies

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

The Fabulous Nuclear Odyssey of Belgium

Proposed New Fatigue Design Curves for Carbon and Low-Alloy Steels in High Temperature Water

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

Applicable Contact Force Models for the Discrete Element Method: The Single Particle Perspective

The European Creep Collaborative Committee (ECCC) Approach to Creep Data Assessment

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