Search Results | J. Pressure Vessel Technol.

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Journal Articles

Overview of Nuclear Piping Seismic Verification

Hiroshi Abe, Nilesh Chokshi

J. Pressure Vessel Technol. June 2022, 144(3): 031903.

Paper No: PVT-20-1221

DOI: https://doi.org/10.1115/1.4053831

Published Online: March 24, 2022

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Topics: Design, Pipes, Nuclear power stations, Piping systems, Earthquakes, Stress, Excitation, Earthquake resistant design, Safety

Journal Articles

Static Analysis and Health Monitoring of Pipelines in Nuclear Power Plants With Noise Consideration

Dhrubajyoti Datta

J. Pressure Vessel Technol. June 2022, 144(3): 034501.

Paper No: PVT-20-1206

DOI: https://doi.org/10.1115/1.4053882

Published Online: March 8, 2022

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Topics: Noise (Sound), Nuclear power stations, Pipelines, Pipes, Pressure, Stress, Springs, Stiffness, Structural health monitoring, Temperature gradient

Journal Articles

Dynamic Modeling of Spent Fuel Rack Pool Subjected to Seismic Excitation Considering Fluid–Structure Interaction

Guillaume Ricciardi, Heung Seok Kang, Dong Seok Oh, Kang Hee Lee

J. Pressure Vessel Technol. December 2021, 143(6): 061903.

Paper No: PVT-20-1240

DOI: https://doi.org/10.1115/1.4051367

Published Online: July 9, 2021

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Topics: Engineering simulation, Excitation, Fluid structure interaction, Fluids, Friction, Simulation, Spent nuclear fuels, Water, Displacement, Dynamic modeling

Journal Articles

An Improved Phased Array Ultrasonic Testing Technique for Thick-Wall Polyethylene Pipe Used in Nuclear Power Plant

Yinkang Qin, Jianfeng Shi, Jinyang Zheng, Dongsheng Hou, Weican Guo

J. Pressure Vessel Technol. August 2019, 141(4): 041403.

Paper No: PVT-18-1240

DOI: https://doi.org/10.1115/1.4043384

Published Online: May 8, 2019

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Topics: Acoustics, Computer simulation, Delays, Inspection, Nuclear power stations, Ultrasonic testing, Deflection, Waves

Journal Articles

Prediction and Measurement of Sealing Properties of Joints Between Wavy Metal Surfaces

Julien Bourniquel, Didier Lasseux, Jean-Francois Rit

J. Pressure Vessel Technol. October 2018, 140(5): 051203.

Paper No: PVT-17-1258

DOI: https://doi.org/10.1115/1.4040894

Published Online: August 2, 2018

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Topics: Boundary element methods, Flow (Dynamics), Fluid dynamics, Leakage, Manufacturing, Metal surfaces, Microscopy, Pressure, Pressure drop, Sealing (Process)

Journal Articles

A New Methodology for Structural Reliability Assessment of the Heat Exchanger Tubes of WWER Steam Generators

Igor Orynyak, Maksym Zarazovskii, Mykhaylo Borodii

J. Pressure Vessel Technol. June 2017, 139(3): 031208.

Paper No: PVT-16-1071

DOI: https://doi.org/10.1115/1.4035414

Published Online: February 3, 2017

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Topics: Circuits, Fracture (Materials), Heat exchangers, Leakage, Nuclear power stations, Pressure, Probability, Boilers, Shapes, Statistics

Journal Articles

Ultrasonic Inspection of Electrofusion Joints of Large Polyethylene Pipes in Nuclear Power Plants

Jinyang Zheng, Dongsheng Hou, Weican Guo, Xiaoming Miao, Yaoda Zhou, Jianfeng Shi

J. Pressure Vessel Technol. December 2016, 138(6): 060908.

Paper No: PVT-15-1156

DOI: https://doi.org/10.1115/1.4033448

Published Online: July 18, 2016

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Topics: Inspection, Nuclear power stations, Pipes

Journal Articles

Mechanical Properties Variations and Comparative Analysis of Dissimilar Metal Pipe Welds in Pressure Vessel System of Nuclear Plants

Dinesh W. Rathod, Sunil Pandey, P. K. Singh, Rajesh Prasad

J. Pressure Vessel Technol. February 2016, 138(1): 011403.

Paper No: PVT-15-1055

DOI: https://doi.org/10.1115/1.4031129

Published Online: September 7, 2015

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Topics: Base metals, Fracture (Materials), Mechanical properties, Mechanical testing, Metals, Microhardness, Nuclear power stations, Pipes, Pressure vessel systems, Steel

Journal Articles

Critical Section Selection Methodology for the U.S. EPR TM Standard Nuclear Power Plant

Se-Kwon Jung, Adam Goodman, Joseph Harrold, Nawar Alchaar

J. Pressure Vessel Technol. August 2013, 135(4): 044501.

Paper No: PVT-11-1131

DOI: https://doi.org/10.1115/1.4023737

Published Online: June 11, 2013

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Topics: Design, Nuclear power stations, Safety, Slabs, Stress, Shear (Mechanics)

Journal Articles

Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics (PVP2010-25195)

Bo-Yi Chen, Chin-Cheng Huang, Hsoung-Wei Chou, Ru-Feng Liu, Hsien-Chou Lin

J. Pressure Vessel Technol. February 2013, 135(1): 011206.

Paper No: PVT-12-1003

DOI: https://doi.org/10.1115/1.4007292

Published Online: December 17, 2012

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Topics: Boiling water reactors, Design, Failure, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear power stations, Pressure vessels, Probability, Transients (Dynamics)

Journal Articles

Nuclear Power in Europe 2012

Luc H. Geraets, Ir. Yves A. Crommelynck

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

DOI: https://doi.org/10.1115/1.4007979

Published Online: October 25, 2012

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

Journal Articles

Moving Beyond Nondestructive Examination to Proactive Management of Materials Degradation

Leonard J. Bond

J. Pressure Vessel Technol. February 2012, 134(1): 014501.

DOI: https://doi.org/10.1115/1.4005056

Published Online: December 20, 2011

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Topics: Nondestructive evaluation, Nuclear power stations, Damage, Materials management, Inspection

Journal Articles

A Methodology for Online Fatigue Monitoring With Consideration of Temperature-Dependent Material Properties Using Artificial Parameter Method

Hengliang Zhang, Yangheng Xiong, Chu Nie, Danmei Xie, Kunfeng Sun

J. Pressure Vessel Technol. February 2012, 134(1): 011201.

DOI: https://doi.org/10.1115/1.4004627

Published Online: December 1, 2011

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Topics: Fatigue, Finite element methods, Materials properties, Stress, Temperature, Thermal stresses, Nuclear power stations, Transients (Dynamics)

Journal Articles

Erratum: “Application of Negligible Creep Criteria to Candidate Materials for HTGR Pressure Vessel” ( Journal of Pressure Vessel Technology, 2011, 133, p. 021103 )

R. I. Jetter, T.-L. Sham, R. W. Swindeman

J. Pressure Vessel Technol. October 2011, 133(5): 057001.

DOI: https://doi.org/10.1115/1.4004509

Published Online: August 23, 2011

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Topics: Creep, Pressure vessels, Very high temperature reactors, Nuclear power stations

Journal Articles

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

Paolo Contri, Bernhard Elsing

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

DOI: https://doi.org/10.1115/1.4002553

Published Online: April 6, 2011

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

Journal Articles

Materials Databases and Knowledge Management for Advanced Nuclear Technologies

Wolfgang Hoffelner

J. Pressure Vessel Technol. February 2011, 133(1): 014505.

DOI: https://doi.org/10.1115/1.4002262

Published Online: January 21, 2011

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Topics: Collaboration, Databases, Knowledge management, Design, Nuclear power stations

Journal Articles

Material Selection Methodology Used in Czech NPP

Karel Matocha

J. Pressure Vessel Technol. February 2011, 133(1): 014501.

DOI: https://doi.org/10.1115/1.4001652

Published Online: January 20, 2011

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Topics: Maintenance, Nuclear power stations, Materials properties

Journal Articles

The Fabulous Nuclear Odyssey of Belgium

Luc H. Geraets, Ph.D.

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

DOI: https://doi.org/10.1115/1.3106035

Published Online: April 6, 2009

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

Journal Articles

Guest Editorial

Kohei Suzuki, Luc H. Geraets

J. Pressure Vessel Technol. November 2006, 128(4): 485.

DOI: https://doi.org/10.1115/1.2349584

Published Online: November 1, 2006

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Topics: Earthquake engineering, Earthquake resistant design, Earthquakes, Energy industry, Engineering research, Engineering standards, Engineering teachers, High pressure (Physics), Japan Society of Mechanical Engineers, Leadership

Journal Articles

Eddy Current Examination of Fatigue Cracks in Inconel Welds

Weiying Cheng, Ichiro Komura, Mitsuharu Shiwa, Shigeru Kanemoto

J. Pressure Vessel Technol. February 2007, 129(1): 169–174.

DOI: https://doi.org/10.1115/1.2435718

Published Online: July 11, 2006

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Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Electrical discharge machining, Fatigue cracks, Fracture (Materials), Probes, Signals, Welded joints, Base metals, Eddy current testing

2 3 4

Journal citation

NARROW

Overview of Nuclear Piping Seismic Verification

Static Analysis and Health Monitoring of Pipelines in Nuclear Power Plants With Noise Consideration

Dynamic Modeling of Spent Fuel Rack Pool Subjected to Seismic Excitation Considering Fluid–Structure Interaction

An Improved Phased Array Ultrasonic Testing Technique for Thick-Wall Polyethylene Pipe Used in Nuclear Power Plant

Prediction and Measurement of Sealing Properties of Joints Between Wavy Metal Surfaces

A New Methodology for Structural Reliability Assessment of the Heat Exchanger Tubes of WWER Steam Generators

Ultrasonic Inspection of Electrofusion Joints of Large Polyethylene Pipes in Nuclear Power Plants

Mechanical Properties Variations and Comparative Analysis of Dissimilar Metal Pipe Welds in Pressure Vessel System of Nuclear Plants

Critical Section Selection Methodology for the U.S. EPR TM Standard Nuclear Power Plant

Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics (PVP2010-25195)

Nuclear Power in Europe 2012

Moving Beyond Nondestructive Examination to Proactive Management of Materials Degradation

A Methodology for Online Fatigue Monitoring With Consideration of Temperature-Dependent Material Properties Using Artificial Parameter Method

Erratum: “Application of Negligible Creep Criteria to Candidate Materials for HTGR Pressure Vessel” ( Journal of Pressure Vessel Technology, 2011, 133, p. 021103 )

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

Materials Databases and Knowledge Management for Advanced Nuclear Technologies

Material Selection Methodology Used in Czech NPP

The Fabulous Nuclear Odyssey of Belgium

Guest Editorial

Eddy Current Examination of Fatigue Cracks in Inconel Welds

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