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Journal Articles

Determination and Sensitivity Analysis of Target Flaw Sizes for Performance Demonstration of Cast Austenitic Stainless Steel Pipe by Probabilistic Fracture Mechanics

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Daiki Takagoshi, Yuji Momotani, Yuichiro Nomura, Wataru Nishi, Takatoshi Hirota, Kiminobu Hojo
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2025, 147(2): 021303.
Paper No: PVT-23-1142
https://doi.org/10.1115/1.4067591
Published Online: January 29, 2025
View Articletitled, Determination and Sensitivity Analysis of Target Flaw Sizes for Performance Demonstration of Cast Austenitic Stainless Steel Pipe by Probabilistic Fracture Mechanics
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Topics: Failure, Fracture (Materials), Fracture (Process), Fracture mechanics, Fracture toughness, Mechanical properties, Pipes, Probability, Stress, Tensile strength
Journal Articles

Fatigue Damage Management According to Performance-Based Maintenance Concept

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Masayuki Kamaya
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2022, 144(3): 031301.
Paper No: PVT-20-1183
https://doi.org/10.1115/1.4052878
Published Online: December 6, 2021
View Articletitled, Fatigue Damage Management According to Performance-Based Maintenance Concept
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Topics: Fatigue life, Fracture (Materials), Maintenance, Pressurized water reactors, Water, Fatigue damage, Inspection
Journal Articles

Cyclic Ramberg–Osgood Parameters of 316SS Weld Metal Under In-Air and PWR-Water Environments

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Jae Phil Park, Subhasish Mohanty, Chi Bum Bahn
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2021, 143(5): 051507.
Paper No: PVT-19-1217
https://doi.org/10.1115/1.4050219
Published Online: July 19, 2021
View Articletitled, Cyclic Ramberg–Osgood Parameters of 316SS Weld Metal Under In-Air and PWR-Water Environments
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Topics: Cycles, Fatigue life, Fatigue testing, Hardening, Metals, Plasticity, Pressurized water reactors, Stress, Water, Fatigue
Journal Articles

Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction

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Hisashi Takamizawa, Yutaka Nishiyama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2021, 143(5): 051502.
Paper No: PVT-20-1142
https://doi.org/10.1115/1.4050317
Published Online: March 22, 2021
View Articletitled, Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction
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Topics: Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Surveillance, Steel, Temperature, Uncertainty
Journal Articles

Influence of Mean Strain on Fatigue Life of Stainless Steel in Pressurized Water Reactor Water Environment

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Masayuki Kamaya
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2021, 143(4): 041505.
Paper No: PVT-19-1125
https://doi.org/10.1115/1.4050089
Published Online: March 19, 2021
View Articletitled, Influence of Mean Strain on Fatigue Life of Stainless Steel in Pressurized Water Reactor Water Environment
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Topics: Fatigue life, Pressurized water reactors, Stainless steel, Stress, Water, Work hardening, Fatigue testing, Surface roughness
Journal Articles

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

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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 Articletitled, 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

Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments

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Ernest D. Eason, Raj Pathania, Anders Jenssen, Dennis P. Weakland
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2021, 143(2): 021202.
Paper No: PVT-19-1261
https://doi.org/10.1115/1.4047878
Published Online: September 15, 2020
View Articletitled, Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments
Open the PDF for Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments in another window
Topics: Calibration, Fracture (Materials), Heat, Inspection, Irradiation (Radiation exposure), Light water reactors, Pressurized water reactors, Stainless steel, Stress corrosion cracking, Yield stress
Journal Articles

Incefa-Plus Project: Lessons Learned From the Project Data and Impact on Existing Fatigue Assessment Procedures

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Sam Cuvilliez, Alec McLennan, Kevin Mottershead, Jonathan Mann, Matthias Bruchhausen
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2020, 142(6): 061507.
Paper No: PVT-20-1046
https://doi.org/10.1115/1.4047273
Published Online: August 5, 2020
View Articletitled, Incefa-Plus Project: Lessons Learned From the Project Data and Impact on Existing Fatigue Assessment Procedures
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Topics: Design, Fatigue, Finishes, Polishing, Pressurized water reactors, Surface roughness, Electric arc furnaces, Databases
Journal Articles

Mean Stress Effect on Fatigue Properties of Type 316 Stainless Steel in Pressurized Water Reactors Primary Water Environment

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Masayuki Kamaya
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2019, 141(5): 051402.
Paper No: PVT-18-1177
https://doi.org/10.1115/1.4043997
Published Online: July 17, 2019
View Articletitled, Mean Stress Effect on Fatigue Properties of Type 316 Stainless Steel in Pressurized Water Reactors Primary Water Environment
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Topics: Fatigue life, Pressurized water reactors, Stress, Water, Fatigue testing, Stainless steel
Journal Articles

Numerical Analysis of Subcooled Water Flashing Flow From a Pressurized Water Reactor Steam Generator Through an Abruptly Broken Main Feed Water Pipe

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Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Jongkap Kim
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. August 2019, 141(4): 044501.
Paper No: PVT-18-1164
https://doi.org/10.1115/1.4043297
Published Online: April 25, 2019
View Articletitled, Numerical Analysis of Subcooled Water Flashing Flow From a Pressurized Water Reactor Steam Generator Through an Abruptly Broken Main Feed Water Pipe
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Topics: Feedwater, Flashing, Flow (Dynamics), Pipes, Pressure, Subcooling, Transients (Dynamics), Water, Numerical analysis, Computer simulation
Journal Articles

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

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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. October 2018, 140(5): 051403.
Paper No: PVT-18-1061
https://doi.org/10.1115/1.4040790
Published Online: August 2, 2018
View Articletitled, Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading
Open the PDF for Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading in another window
Topics: Fatigue, Fatigue life, Finite element analysis, Modeling, Stress, Hardening, Nuclear reactors, Stainless steel, Stress analysis (Engineering), Pressurized water reactors
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

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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 Articletitled, 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
Open the PDF for 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 in another window
Topics: Fatigue, Fatigue testing, Pressurized water reactors, Stress, Water, Coolants, Cycles
Journal Articles

Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model

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Jong Chull Jo, Jae Jun Jeong, Frederick J. Moody
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2017, 139(3): 031302.
Paper No: PVT-16-1052
https://doi.org/10.1115/1.4034468
Published Online: October 11, 2016
View Articletitled, Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model
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Topics: Computational fluid dynamics, Feedwater, Flow (Dynamics), Nozzles, Pressure, Transients (Dynamics), Water, Pressurized water reactors, Pipes, Waves
Journal Articles

Effects of a Venturi-Type Flow Restrictor on the Thermal-Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break

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Jong Chull Jo, Frederick J. Moody
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2016, 138(4): 041304.
Paper No: PVT-15-1204
https://doi.org/10.1115/1.4032282
Published Online: April 28, 2016
View Articletitled, Effects of a Venturi-Type Flow Restrictor on the Thermal-Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break
Open the PDF for Effects of a Venturi-Type Flow Restrictor on the Thermal-Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break in another window
Topics: Flow (Dynamics), Pressure, Steam, Transients (Dynamics), Venturi tubes, Computational fluid dynamics, Pressurized water reactors
Journal Articles

Effects of Boiling Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels

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Paul Wilhelm, Paul Steinmann, Jürgen Rudolph
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2016, 138(3): 031406.
Paper No: PVT-15-1189
https://doi.org/10.1115/1.4032651
Published Online: February 22, 2016
View Articletitled, Effects of Boiling Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
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Topics: Boiling water reactors, Fatigue, Fatigue life, Temperature, Water, Stainless steel, Pressurized water reactors
Journal Articles

Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel

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Kuan-Rong Huang, Chin-Cheng Huang, Hsiung-Wei Chou
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2016, 138(3): 031202.
Paper No: PVT-15-1089
https://doi.org/10.1115/1.4032110
Published Online: February 8, 2016
View Articletitled, Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel
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Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Pressure, Pressure vessels, Pressurized water reactors, Probability, Radiation (Physics), Reliability, Stress
Journal Articles

Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels

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Paul Wilhelm, Jürgen Rudolph, Paul Steinmann
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2015, 137(6): 061404.
Paper No: PVT-14-1194
https://doi.org/10.1115/1.4029832
Published Online: December 1, 2015
View Articletitled, Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
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Topics: Fatigue, Fatigue life, Pressurized water reactors, Stainless steel, Temperature, Cycles, Water, Databases
Journal Articles

Prediction of Weld Residual Stress in a Pressurized Water Reactor Pressurizer Surge Nozzle

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Akira Maekawa, Atsushi Kawahara, Hisashi Serizawa, Hidekazu Murakawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2016, 138(2): 021401.
Paper No: PVT-14-1196
https://doi.org/10.1115/1.4031376
Published Online: October 6, 2015
View Articletitled, Prediction of Weld Residual Stress in a Pressurized Water Reactor Pressurizer Surge Nozzle
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Topics: Heat, Stress, Stress analysis (Engineering), Welding, Pressurized water reactors, Nozzles, Simulation, Metals, Surges, Computation
Journal Articles

Analytical Study of Flow Instability in a Natural Circulation Pressurized Water Reactor Auxiliary Feedwater System

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Jong Chull Jo, Frederick J. Moody, Kyu Sik Do
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. April 2015, 137(2): 024501.
Paper No: PVT-14-1031
https://doi.org/10.1115/1.4027948
Published Online: October 15, 2014
View Articletitled, Analytical Study of Flow Instability in a Natural Circulation Pressurized Water Reactor Auxiliary Feedwater System
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Topics: Condensed matter, Feedwater, Flow instability, Pressurized water reactors, Water, Momentum, Steam, Condensation, Flow (Dynamics)
Journal Articles

Mass, Stiffness, and Damping Identification for a Pressurized Water Reactors Fuel Assembly by a Proper Orthogonal Decomposition Method

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G. Ricciardi, E. Boccaccio
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2014, 136(6): 061303.
Paper No: PVT-13-1107
https://doi.org/10.1115/1.4028559
Published Online: October 14, 2014
View Articletitled, Mass, Stiffness, and Damping Identification for a Pressurized Water Reactors Fuel Assembly by a Proper Orthogonal Decomposition Method
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Topics: Damping, Flow (Dynamics), Fuels, Manufacturing, Stiffness, Displacement, Water, Axial flow, Principal component analysis, Pressurized water reactors