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Journal Articles

Fatigue Damage Management According to Performance-Based Maintenance Concept

Masayuki Kamaya

J. Pressure Vessel Technol. June 2022, 144(3): 031301.

Paper No: PVT-20-1183

DOI: https://doi.org/10.1115/1.4052878

Published Online: December 6, 2021

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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

Jae Phil Park, Subhasish Mohanty, Chi Bum Bahn

J. Pressure Vessel Technol. October 2021, 143(5): 051507.

Paper No: PVT-19-1217

DOI: https://doi.org/10.1115/1.4050219

Published Online: July 19, 2021

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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

Hisashi Takamizawa, Yutaka Nishiyama

J. Pressure Vessel Technol. October 2021, 143(5): 051502.

Paper No: PVT-20-1142

DOI: https://doi.org/10.1115/1.4050317

Published Online: March 22, 2021

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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

Masayuki Kamaya

J. Pressure Vessel Technol. August 2021, 143(4): 041505.

Paper No: PVT-19-1125

DOI: https://doi.org/10.1115/1.4050089

Published Online: March 19, 2021

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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

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

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

Ernest D. Eason, Raj Pathania, Anders Jenssen, Dennis P. Weakland

J. Pressure Vessel Technol. April 2021, 143(2): 021202.

Paper No: PVT-19-1261

DOI: https://doi.org/10.1115/1.4047878

Published Online: September 15, 2020

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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

Sam Cuvilliez, Alec McLennan, Kevin Mottershead, Jonathan Mann, Matthias Bruchhausen

J. Pressure Vessel Technol. December 2020, 142(6): 061507.

Paper No: PVT-20-1046

DOI: https://doi.org/10.1115/1.4047273

Published Online: August 5, 2020

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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

Masayuki Kamaya

J. Pressure Vessel Technol. October 2019, 141(5): 051402.

Paper No: PVT-18-1177

DOI: https://doi.org/10.1115/1.4043997

Published Online: July 17, 2019

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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

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Jongkap Kim

J. Pressure Vessel Technol. August 2019, 141(4): 044501.

Paper No: PVT-18-1164

DOI: https://doi.org/10.1115/1.4043297

Published Online: April 25, 2019

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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

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

J. Pressure Vessel Technol. October 2018, 140(5): 051403.

Paper No: PVT-18-1061

DOI: https://doi.org/10.1115/1.4040790

Published Online: August 2, 2018

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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

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

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

Jong Chull Jo, Jae Jun Jeong, Frederick J. Moody

J. Pressure Vessel Technol. June 2017, 139(3): 031302.

Paper No: PVT-16-1052

DOI: https://doi.org/10.1115/1.4034468

Published Online: October 11, 2016

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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

Jong Chull Jo, Frederick J. Moody

J. Pressure Vessel Technol. August 2016, 138(4): 041304.

Paper No: PVT-15-1204

DOI: https://doi.org/10.1115/1.4032282

Published Online: April 28, 2016

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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

Paul Wilhelm, Paul Steinmann, Jürgen Rudolph

J. Pressure Vessel Technol. June 2016, 138(3): 031406.

Paper No: PVT-15-1189

DOI: https://doi.org/10.1115/1.4032651

Published Online: February 22, 2016

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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

Kuan-Rong Huang, Chin-Cheng Huang, Hsiung-Wei Chou

J. Pressure Vessel Technol. June 2016, 138(3): 031202.

Paper No: PVT-15-1089

DOI: https://doi.org/10.1115/1.4032110

Published Online: February 8, 2016

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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

Paul Wilhelm, Jürgen Rudolph, Paul Steinmann

J. Pressure Vessel Technol. December 2015, 137(6): 061404.

Paper No: PVT-14-1194

DOI: https://doi.org/10.1115/1.4029832

Published Online: December 1, 2015

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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

Akira Maekawa, Atsushi Kawahara, Hisashi Serizawa, Hidekazu Murakawa

J. Pressure Vessel Technol. April 2016, 138(2): 021401.

Paper No: PVT-14-1196

DOI: https://doi.org/10.1115/1.4031376

Published Online: October 6, 2015

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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

Jong Chull Jo, Frederick J. Moody, Kyu Sik Do

J. Pressure Vessel Technol. April 2015, 137(2): 024501.

Paper No: PVT-14-1031

DOI: https://doi.org/10.1115/1.4027948

Published Online: October 15, 2014

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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

G. Ricciardi, E. Boccaccio

J. Pressure Vessel Technol. December 2014, 136(6): 061303.

Paper No: PVT-13-1107

DOI: https://doi.org/10.1115/1.4028559

Published Online: October 14, 2014

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Topics: Damping, Flow (Dynamics), Fuels, Manufacturing, Stiffness, Displacement, Water, Axial flow, Principal component analysis, Pressurized water reactors

Journal Articles

Fatigue Life of the Strain Hardened Austenitic Stainless Steel in Simulated Pressurized Water Reactor Primary Water

Nicolas Huin, Kazuya Tsutsumi, Thierry Couvant, Gilbert Henaff, Jose Mendez

J. Pressure Vessel Technol. June 2014, 136(3): 031405.

Paper No: PVT-12-1144

DOI: https://doi.org/10.1115/1.4026521

Published Online: April 4, 2014

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Topics: Cycles, Fatigue life, Pressurized water reactors, Water, Stainless steel, Fatigue, Temperature, Stress

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Journal citation

NARROW

Fatigue Damage Management According to Performance-Based Maintenance Concept

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Fatigue Life of the Strain Hardened Austenitic Stainless Steel in Simulated Pressurized Water Reactor Primary Water

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