Search Results | J. Pressure Vessel Technol.

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Journal Articles

Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

Kai Lu, Jinya Katsuyama, Koichi Masaki, Tadashi Watanabe, Yinsheng Li

J. Pressure Vessel Technol. June 2021, 143(3): 031704.

Paper No: PVT-20-1128

DOI: https://doi.org/10.1115/1.4049048

Published Online: November 18, 2020

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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Pressurized water reactors, Probability, Reactor vessels, Water temperature

Journal Articles

Methodology for Stress-Controlled Fatigue Test Under In-Air and Pressurized Water Reactor Coolant Water Condition and to Evaluate the Effect of Pressurized Water Reactor Water and Loading Rate on Ratcheting

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

J. Pressure Vessel Technol. June 2018, 140(3): 031403.

Paper No: PVT-17-1236

DOI: https://doi.org/10.1115/1.4039345

Published Online: April 4, 2018

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Topics: Fatigue, Fatigue testing, Pressurized water reactors, Stress, Water, Coolants, Cycles

Journal Articles

Thermomechanical Behavior of Pressure Tube Under Small Break Loss of Coolant Accident for PHWR

Ashwini K. Yadav, Ravi Kumar, Akhilesh Gupta, B. Chatterjee, P. Majumdar, D. Mukhopadhyay

J. Pressure Vessel Technol. August 2013, 135(4): 041601.

Paper No: PVT-12-1098

DOI: https://doi.org/10.1115/1.4024580

Published Online: June 11, 2013

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Topics: Pressure, Temperature, Heat, Heavy water reactors, Deformation, Accidents, Fuels, Coolants, Thermomechanics

Journal Articles

Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions

Dieter Beukelmann, Wenfeng Guo, Wieland Holzer, Robert Kauer, Wolfgang Münch, Christoph Reichel, Peter Schöner

J. Pressure Vessel Technol. February 2012, 134(1): 011302.

DOI: https://doi.org/10.1115/1.4004799

Published Online: December 8, 2011

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Topics: Accidents, Computational fluid dynamics, Coolants, Corners (Structural elements), Flanges, Fracture (Materials), Fracture mechanics, Nozzles, Plumes (Fluid dynamics), Reactor vessels

Journal Articles

Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study

P. Majumdar, B. Chatterjee, G. Nandan, D. Mukhopadhyay, H. G. Lele

J. Pressure Vessel Technol. February 2011, 133(1): 014503.

DOI: https://doi.org/10.1115/1.4001921

Published Online: January 20, 2011

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Topics: Pressure, Temperature, Accidents, Coolants, Deformation

Journal Articles

Root Cause Analysis of SI Nozzle Thermal Sleeve Breakaway Failures Occurring at PWR Plants

Jong Chull Jo, Myung Jo Jhung, Seon Oh Yu, Hho Jung Kim, Young Gill Yune

J. Pressure Vessel Technol. February 2009, 131(1): 011304.

DOI: https://doi.org/10.1115/1.2980017

Published Online: November 24, 2008

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Topics: Computational fluid dynamics, Flow (Dynamics), Nozzles, Pipes, Pressure, Transients (Dynamics), Failure, Vibration, Coolants, Pressurized water reactors

Journal Articles

Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident

Dieter Siegele, Igor Varfolomeyev, Gerhard Nagel

J. Pressure Vessel Technol. August 2008, 130(3): 031403.

DOI: https://doi.org/10.1115/1.2937759

Published Online: June 6, 2008

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Topics: Brittleness, Coolants, Corners (Structural elements), Failure, Flanges, Fracture (Materials), Nozzles, Stress, Transients (Dynamics), Accidents

Journal Articles

Destruction of Cryogenic Pressure Vessel and Piping by Shock Wave

Toshiaki Watanabe, Kazuyuki Hokamoto, Shigeru Itoh

J. Pressure Vessel Technol. February 2007, 129(1): 38–42.

DOI: https://doi.org/10.1115/1.2388999

Published Online: March 30, 2006

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Topics: Flashing, Nitrogen, Pipes, Pressure vessels, Shock waves, Temperature, Thermal insulation, Pressure, Coolants

Journal Articles

Laboratory Heat Transfer Experiments on a 155 mm Compound Gun Tube With Full Length Integral Mid-Wall Cooling Channels

Mark Bass, Rolf R. de Swardt

J. Pressure Vessel Technol. May 2006, 128(2): 279–284.

DOI: https://doi.org/10.1115/1.2179434

Published Online: January 17, 2006

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Topics: Cooling, Heat exchangers, Flow (Dynamics), Temperature, Coolants, Gun barrels, Heat

Journal Articles

Analysis of the Thermal Hydraulic Consequences Following Common Mode Pump Seizure in a Nuclear Power Plant

B. Chatterjee, S. K. Gupta, H. S. Kushwaha, V. Venkat Raj

J. Pressure Vessel Technol. November 2002, 124(4): 415–417.

DOI: https://doi.org/10.1115/1.1465437

Published Online: November 8, 2002

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Topics: Heat transfer, Nuclear power stations, Pressure, Pumps, Coolants, Heavy water reactors, Flow (Dynamics), Heat, Earthquakes

Journal Articles

Thermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR

D. Mukhopadhyay, P. Majumdar, G. Behera, S. K. Gupta, V. Venkat Raj

J. Pressure Vessel Technol. May 2002, 124(2): 161–167.

DOI: https://doi.org/10.1115/1.1463036

Published Online: May 1, 2002

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Topics: Damage, Flow (Dynamics), Fuels, Heat, Heavy water reactors, Temperature, Thermal analysis, Simulation, Pressure, Coolants

Journal Articles

Prediction of Materials Damage History From Stress Corrosion Cracking in Boiling Water Reactors

Iouri Balachov, Digby Macdonald, Bernhard Stellwag, Norbert Henzel, Renate Kilian

J. Pressure Vessel Technol. February 2000, 122(1): 45–49.

DOI: https://doi.org/10.1115/1.556148

Published Online: October 11, 1999

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Topics: Boiling water reactors, Coolants, Damage, Fracture (Materials), Stress corrosion cracking, Pumps, Hydrogen, Circuits, Water chemistry, Stainless steel

Journal Articles

Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments

O. K. Chopra, W. J. Shack

J. Pressure Vessel Technol. February 1999, 121(1): 49–60.

DOI: https://doi.org/10.1115/1.2883667

Published Online: February 1, 1999

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Topics: Alloys, Carbon, Fatigue cracks, Light water reactors, Steel, Fatigue, Fracture (Materials), Design, Coolants, Fatigue life

Journal Articles

Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels

O. K. Chopra, D. J. Gavenda

J. Pressure Vessel Technol. May 1998, 120(2): 116–121.

DOI: https://doi.org/10.1115/1.2842228

Published Online: May 1, 1998

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Topics: Coolants, Fatigue, Light water reactors, Stainless steel, Water, Steel, Fatigue life, Fatigue cracks, Fatigue testing, Oxygen

Journal Articles

Evaluation of Accumulated Fatigue in Metals Due to Random Oscillating Thermal Stresses

I. Klevtsov, R. Crane

J. Pressure Vessel Technol. February 1998, 120(1): 43–50.

DOI: https://doi.org/10.1115/1.2841883

Published Online: February 1, 1998

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Topics: Metal fatigue, Thermal stresses, Oscillations, Stress, Temperature, Boilers, Boiling, Boundary-value problems, Computational methods, Coolants

Journal Articles

Fracture Analysis of Multiple Cracks in a Spinning Cylinder Experiment

J. A. Keeney, B. R. Bass

J. Pressure Vessel Technol. May 1997, 119(2): 232–235.

DOI: https://doi.org/10.1115/1.2842290

Published Online: May 1, 1997

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Topics: Cylinders, Fracture (Materials), Spin (Aerodynamics), Spinning (Textile), Temperature, Coolants, Finite element analysis, Engineering standards, Reactor vessels, Steel

Journal Articles

Fracture Analysis of the NESC-1 Spinning Cylinder Experiment

J. A. Keeney, B. R. Bass

J. Pressure Vessel Technol. February 1997, 119(1): 52–56.

DOI: https://doi.org/10.1115/1.2842266

Published Online: February 1, 1997

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Topics: Cylinders, Fracture (Materials), Spin (Aerodynamics), Spinning (Textile), Temperature, Coolants, Probability, Thermal shock, Wall thickness, Finite element analysis

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

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

DOI: https://doi.org/10.1115/1.2842192

Published Online: August 1, 1996

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

Journal Articles

An Experimental Study of Assessment of Weld Quality on Fatigue Reliability Analysis of a Nuclear Pressure Vessel

Shu-Ho Dai

J. Pressure Vessel Technol. November 1993, 115(4): 411–414.

DOI: https://doi.org/10.1115/1.2929549

Published Online: November 1, 1993

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Topics: Event history analysis, Fatigue, Reactor vessels, Boilers, Nuclear power stations, China, Engineering prototypes, Safety, ASME Boiler and Pressure Vessel Code, Construction

Journal Articles

A Probabilistic Approach to the Evaluation of the PTS Issue

R. D. Cheverton, D. L. Selby

J. Pressure Vessel Technol. November 1992, 114(4): 396–404.

DOI: https://doi.org/10.1115/1.2929245

Published Online: November 1, 1992

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Topics: Coolants, Failure, Fluid films, Fracture mechanics, Heat transfer, Plant design, Pressure, Pressurized water reactors, Probability, Shock (Mechanics)

Journal citation

NARROW

Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

Methodology for Stress-Controlled Fatigue Test Under In-Air and Pressurized Water Reactor Coolant Water Condition and to Evaluate the Effect of Pressurized Water Reactor Water and Loading Rate on Ratcheting

Thermomechanical Behavior of Pressure Tube Under Small Break Loss of Coolant Accident for PHWR

Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions

Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study

Root Cause Analysis of SI Nozzle Thermal Sleeve Breakaway Failures Occurring at PWR Plants

Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident

Destruction of Cryogenic Pressure Vessel and Piping by Shock Wave

Laboratory Heat Transfer Experiments on a 155 mm Compound Gun Tube With Full Length Integral Mid-Wall Cooling Channels

Analysis of the Thermal Hydraulic Consequences Following Common Mode Pump Seizure in a Nuclear Power Plant

Thermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR

Prediction of Materials Damage History From Stress Corrosion Cracking in Boiling Water Reactors

Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments

Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels

Evaluation of Accumulated Fatigue in Metals Due to Random Oscillating Thermal Stresses

Fracture Analysis of Multiple Cracks in a Spinning Cylinder Experiment

Fracture Analysis of the NESC-1 Spinning Cylinder Experiment

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

An Experimental Study of Assessment of Weld Quality on Fatigue Reliability Analysis of a Nuclear Pressure Vessel

A Probabilistic Approach to the Evaluation of the PTS Issue

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