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Journal Articles

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP Regarding Stress Corrosion Cracking in Nickel Based Alloy Weld Joint of Piping System in Boiling Water Reactor

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li

J. Pressure Vessel Technol. February 2022, 144(1): 011506.

Paper No: PVT-21-1094

DOI: https://doi.org/10.1115/1.4052449

Published Online: October 8, 2021

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Topics: Alloys, Boiling water reactors, Failure, Fracture (Materials), Nickel, Probability, Sensitivity analysis, Piping systems, Stress corrosion cracking, Leakage

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

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

Development of Boiling Water Reactor Steam Dryer Loading Evaluation Methods Through Scale Model Tests Under Actual Steam Conditions

Shiro Takahashi, Keita Okuyama, Akinori Tamura, Yasuhiro Mabuchi, Teppei Kubota, Kazuhiro Yoshikawa

J. Pressure Vessel Technol. October 2014, 136(5): 051307.

Paper No: PVT-13-1151

DOI: https://doi.org/10.1115/1.4026580

Published Online: August 19, 2014

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Topics: Acoustics, Boiling water reactors, Flow (Dynamics), Pipes, Pressure, Resonance, Steam, Fluids

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

A Risk-Informed Methodology for ASME Section XI, Appendix G

Ronald Gamble, William Server, Bruce Bishop, Nathan Palm, Carol Heinecke

J. Pressure Vessel Technol. June 2012, 134(3): 031002.

DOI: https://doi.org/10.1115/1.4006580

Published Online: May 18, 2012

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Topics: Boiling water reactors, Heat, Leakage, Pressure, Pressurized water reactors, Risk, Temperature, Vessels, Irradiation (Radiation exposure), Reactor vessels

Journal Articles

Review and Consideration of Unsettled Problems on Evaluation of Fatigue Damage in LWR Water

Makoto Higuchi, Katsumi Sakaguchi

J. Pressure Vessel Technol. February 2007, 129(1): 186–194.

DOI: https://doi.org/10.1115/1.2409316

Published Online: June 1, 2006

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Topics: Fatigue, Fatigue life, Stainless steel, Water, Light water reactors, Fatigue damage, Carbon, Boiling water reactors, Steel, Flow (Dynamics)

Journal Articles

Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels

J. A. Wang, S. Konduri, N. S. V. Rao

J. Pressure Vessel Technol. February 2005, 127(1): 98–104.

DOI: https://doi.org/10.1115/1.1858926

Published Online: March 15, 2005

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Topics: Boiling water reactors, Embrittlement, Uncertainty, Radiation (Physics), Steel

Journal Articles

A Proposal of Fatigue Life Correction Factor F en for Austenitic Stainless Steels in LWR Water Environments

Makoto Higuchi, Kazuya Tsutsumi, Akihiko Hirano, Katsumi Sakaguchi

J. Pressure Vessel Technol. November 2003, 125(4): 403–410.

DOI: https://doi.org/10.1115/1.1613945

Published Online: November 4, 2003

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

Journal Articles

Fatigue Crack Growth Curve for Austenitic Stainless Steels in BWR Environment

M. Itatani, M. Asano, M. Kikuchi, S. Suzuki, K. Iida,, Professor Emeritus of The University of Tokyo

J. Pressure Vessel Technol. May 2001, 123(2): 166–172.

DOI: https://doi.org/10.1115/1.1358841

Published Online: December 19, 2000

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Topics: Boiling water reactors, Fatigue cracks, Stainless steel, Stress, Water

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

Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

G. L. Stevens, S. Ranganath

J. Pressure Vessel Technol. August 1991, 113(3): 349–357.

DOI: https://doi.org/10.1115/1.2928766

Published Online: August 1, 1991

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Topics: Fatigue, Life extension, Nuclear reactors, Stress, Computers, Temperature, Boiling water reactors, Monitoring systems, Feedwater, Finite element analysis

Journal Articles

Strength Aspects of Safety and Life Extension of RBMK Reactors

S. E. Bougaenko, E. Yu. Rivkin, B. S. Rodchenkov

J. Pressure Vessel Technol. May 1991, 113(2): 141–144.

DOI: https://doi.org/10.1115/1.2928738

Published Online: May 1, 1991

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Topics: Boiling water reactors, Circuits, Coolants, Design, Fracture mechanics, Graphite, Leak-before-break, Life extension, Pipelines, Safety

Journal Articles

Prediction of Environmental and Strain-Rate Effects on the Stress Corrosion Cracking of Austenitic Stainless Steels

P. S. Maiya

J. Pressure Vessel Technol. February 1987, 109(1): 116–123.

DOI: https://doi.org/10.1115/1.3264843

Published Online: February 1, 1987

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Topics: Stainless steel, Stress corrosion cracking, Boiling water reactors, Corrosion, Fracture mechanics, High temperature, Oxygen, Water

Journal Articles

Experimental Study on Crack Growth Behavior for Austenitic Stainless Steel in High Temperature Pure Water

M. Hishida, M. Saito, K. Hasegawa, K. Enomoto, Y. Matsuo

J. Pressure Vessel Technol. May 1986, 108(2): 226–233.

DOI: https://doi.org/10.1115/1.3264773

Published Online: May 1, 1986

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Topics: Fracture (Materials), High temperature, Stainless steel, Water, Boiling water reactors, Corrosion, Crack propagation, Stress, Stress corrosion cracking, Surface cracks

Journal Articles

Stable Growth and Instability of Circumferential Cracks in Type 304 Stainless Steel Pipes Under Tensile Load

G. Yagawa, Y. Takahashi, K. Kashima, K. Hasegawa, M. Saito, T. Umemoto, N. Sasaki

J. Pressure Vessel Technol. November 1984, 106(4): 405–411.

DOI: https://doi.org/10.1115/1.3264371

Published Online: November 1, 1984

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Topics: Fracture (Materials), Pipes, Stainless steel, Stress, Boiling water reactors, Fracture (Process), Displacement, Finite element analysis, Finite element methods, Machinery

Journal Articles

Computational Method for the Analysis of Valve Transients

T. Siikonen

J. Pressure Vessel Technol. August 1983, 105(3): 227–233.

DOI: https://doi.org/10.1115/1.3264269

Published Online: August 1, 1983

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Topics: Computational methods, Transients (Dynamics), Valves, Boundary-value problems, Dynamics (Mechanics), Boiling water reactors

Journal Articles

Qualification of Induction Heating Stress Improvement for Mitigation of Stress Corrosion Cracking

N. R. Hughes, T. P. Diaz, V. V. Pestanas

J. Pressure Vessel Technol. November 1982, 104(4): 344–350.

DOI: https://doi.org/10.1115/1.3264227

Published Online: November 1, 1982

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Topics: Electromagnetic induction, Heating, Stress, Stress corrosion cracking, Pipes, Boiling water reactors, Compressive stress, Heat, Residual stresses, Strain gages

Journal Articles

The Effect of Induction Heating Stress Remedies on Existing Flaws in Pipes

J. R. Shadley, N. Merah, E. F. Rybicki

J. Pressure Vessel Technol. August 1982, 104(3): 193–197.

DOI: https://doi.org/10.1115/1.3264203

Published Online: August 1, 1982

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Topics: Electromagnetic induction, Heating, Pipes, Stress, Fracture (Materials), Tension, Boiling water reactors, Fracture mechanics, Heat treating (Metalworking), Piping systems

Journal Articles

A Computational Model of Backlay Welding for Controlling Residual Stresses in Welded Pipes

F. W. Brust, E. F. Rybicki

J. Pressure Vessel Technol. August 1981, 103(3): 226–232.

DOI: https://doi.org/10.1115/1.3263395

Published Online: August 1, 1981

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Topics: Pipes, Residual stresses, Welding, Boiling water reactors, Heat, Pipe sizes, Piping systems, Stress, Stress corrosion cracking

Journal citation

NARROW

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP Regarding Stress Corrosion Cracking in Nickel Based Alloy Weld Joint of Piping System in Boiling Water Reactor

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

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

Development of Boiling Water Reactor Steam Dryer Loading Evaluation Methods Through Scale Model Tests Under Actual Steam Conditions

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

A Risk-Informed Methodology for ASME Section XI, Appendix G

Review and Consideration of Unsettled Problems on Evaluation of Fatigue Damage in LWR Water

Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels

A Proposal of Fatigue Life Correction Factor F en for Austenitic Stainless Steels in LWR Water Environments

Fatigue Crack Growth Curve for Austenitic Stainless Steels in BWR Environment

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

Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

Strength Aspects of Safety and Life Extension of RBMK Reactors

Prediction of Environmental and Strain-Rate Effects on the Stress Corrosion Cracking of Austenitic Stainless Steels

Experimental Study on Crack Growth Behavior for Austenitic Stainless Steel in High Temperature Pure Water

Stable Growth and Instability of Circumferential Cracks in Type 304 Stainless Steel Pipes Under Tensile Load

Computational Method for the Analysis of Valve Transients

Qualification of Induction Heating Stress Improvement for Mitigation of Stress Corrosion Cracking

The Effect of Induction Heating Stress Remedies on Existing Flaws in Pipes

A Computational Model of Backlay Welding for Controlling Residual Stresses in Welded Pipes

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