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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2021, 143(3): 031704.
Paper No: PVT-20-1128
https://doi.org/10.1115/1.4049048
Published Online: November 18, 2020
View Article titled, Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2018, 140(3): 031403.
Paper No: PVT-17-1236
https://doi.org/10.1115/1.4039345
Published Online: April 4, 2018
View Article titled, 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
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2013, 135(4): 041601.
Paper No: PVT-12-1098
https://doi.org/10.1115/1.4024580
Published Online: June 11, 2013
View Article titled, Thermomechanical Behavior of Pressure Tube Under Small Break Loss of Coolant Accident for PHWR
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2012, 134(1): 011302.
https://doi.org/10.1115/1.4004799
Published Online: December 8, 2011
View Article titled, Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. February 2011, 133(1): 014503.
https://doi.org/10.1115/1.4001921
Published Online: January 20, 2011
View Article titled, Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2009, 131(1): 011304.
https://doi.org/10.1115/1.2980017
Published Online: November 24, 2008
View Article titled, Root Cause Analysis of SI Nozzle Thermal Sleeve Breakaway Failures Occurring at PWR Plants
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2008, 130(3): 031403.
https://doi.org/10.1115/1.2937759
Published Online: June 6, 2008
View Article titled, Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2007, 129(1): 38–42.
https://doi.org/10.1115/1.2388999
Published Online: March 30, 2006
View Article titled, Destruction of Cryogenic Pressure Vessel and Piping by Shock Wave
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 2006, 128(2): 279–284.
https://doi.org/10.1115/1.2179434
Published Online: January 17, 2006
View Article titled, Laboratory Heat Transfer Experiments on a 155 mm Compound Gun Tube With Full Length Integral Mid-Wall Cooling Channels
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. November 2002, 124(4): 415–417.
https://doi.org/10.1115/1.1465437
Published Online: November 8, 2002
View Article titled, Analysis of the Thermal Hydraulic Consequences Following Common Mode Pump Seizure in a Nuclear Power Plant
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. May 2002, 124(2): 161–167.
https://doi.org/10.1115/1.1463036
Published Online: May 1, 2002
View Article titled, Thermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. February 2000, 122(1): 45–49.
https://doi.org/10.1115/1.556148
Published Online: October 11, 1999
View Article titled, Prediction of Materials Damage History From Stress Corrosion Cracking in Boiling Water Reactors
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Review Articles
J. Pressure Vessel Technol. February 1999, 121(1): 49–60.
https://doi.org/10.1115/1.2883667
Published Online: February 1, 1999
View Article titled, Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1998, 120(2): 116–121.
https://doi.org/10.1115/1.2842228
Published Online: May 1, 1998
View Article titled, Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1998, 120(1): 43–50.
https://doi.org/10.1115/1.2841883
Published Online: February 1, 1998
View Article titled, Evaluation of Accumulated Fatigue in Metals Due to Random Oscillating Thermal Stresses
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1997, 119(2): 232–235.
https://doi.org/10.1115/1.2842290
Published Online: May 1, 1997
View Article titled, Fracture Analysis of Multiple Cracks in a Spinning Cylinder Experiment
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1997, 119(1): 52–56.
https://doi.org/10.1115/1.2842266
Published Online: February 1, 1997
View Article titled, Fracture Analysis of the NESC-1 Spinning Cylinder Experiment
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
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
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1993, 115(4): 411–414.
https://doi.org/10.1115/1.2929549
Published Online: November 1, 1993
View Article titled, An Experimental Study of Assessment of Weld Quality on Fatigue Reliability Analysis of a Nuclear Pressure Vessel
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1992, 114(4): 396–404.
https://doi.org/10.1115/1.2929245
Published Online: November 1, 1992
View Article titled, A Probabilistic Approach to the Evaluation of the PTS Issue
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Topics: Coolants, Failure, Fluid films, Fracture mechanics, Heat transfer, Plant design, Pressure, Pressurized water reactors, Probability, Shock (Mechanics)