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Journal Articles

Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel

Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2021, 143(4): 041501.
Paper No: PVT-18-1049
https://doi.org/10.1115/1.4049693
Published Online: February 11, 2021
View Article titled, Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel
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Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Irradiation (Radiation exposure), Neutrons, Probability, Reactor vessels, Transients (Dynamics), Fracture (Process), Structural elements (Construction)
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
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 Article titled, 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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Topics: Calibration, Fracture (Materials), Heat, Inspection, Irradiation (Radiation exposure), Light water reactors, Pressurized water reactors, Stainless steel, Stress corrosion cracking, Yield stress
Journal Articles

Technical Basis Part 1 for Code Case N-889: Data Selection and Modeling of Stress Corrosion Crack Growth Rates for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments

Ernest D. Eason, Raj Pathania, Anders Jenssen
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2021, 143(2): 021201.
Paper No: PVT-19-1260
https://doi.org/10.1115/1.4047879
Published Online: September 15, 2020
View Article titled, Technical Basis Part 1 for Code Case N-889: Data Selection and Modeling of Stress Corrosion Crack Growth Rates for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments
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Topics: Calibration, Heat, Modeling, Stainless steel, Stress corrosion cracking, Fracture (Materials), Yield stress, Irradiation (Radiation exposure), Light water reactors, Fittings
Journal Articles

Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials

O. K. Chopra, G. L. Stevens, R. Tregoning, A. S. Rao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Review Articles
J. Pressure Vessel Technol. December 2017, 139(6): 060801.
Paper No: PVT-16-1217
https://doi.org/10.1115/1.4035885
Published Online: October 6, 2017
View Article titled, Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials
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Topics: Alloys, Fatigue, Fatigue life, Steel, Fatigue design, Water, Carbon, Temperature, Light water reactors, Stress
Journal Articles

Methodology for Estimating Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels During Service in Light Water Reactors

O. K. Chopra, A. S. Rao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Review Articles
J. Pressure Vessel Technol. August 2016, 138(4): 040801.
Paper No: PVT-15-1130
https://doi.org/10.1115/1.4031909
Published Online: April 28, 2016
View Article titled, Methodology for Estimating Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels During Service in Light Water Reactors
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Topics: Embrittlement, Ferrites (Magnetic materials), Fracture toughness, Neutrons, Temperature, Light water reactors
Journal Articles

U.S. High Fluence Power Reactor Surveillance Data—Past and Future

William L. Server, Timothy C. Hardin, J. Brian Hall, Randy K. Nanstad
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2014, 136(2): 021603.
Paper No: PVT-13-1154
https://doi.org/10.1115/1.4026149
Published Online: January 30, 2014
View Article titled, U.S. High Fluence Power Reactor Surveillance Data—Past and Future
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Topics: Fluence (Radiation measurement), Light water reactors, Surveillance, Embrittlement, Pressurized water reactors
Journal Articles

A Review of the Effects of Coolant Environments on the Fatigue Life of LWR Structural Materials

O. K. Chopra, W. J. Shack
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2009, 131(2): 021409.
https://doi.org/10.1115/1.3027496
Published Online: January 23, 2009
View Article titled, A Review of the Effects of Coolant Environments on the Fatigue Life of LWR Structural Materials
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Topics: Alloys, Carbon, Cycles, Fatigue, Fatigue design, Fatigue life, Light water reactors, Steel, Water, Stress
Journal Articles

Quantitative Estimation of the Growth of Environmentally Assisted Cracks at Flaws in Light Water Reactor Components

H. Xue, Y. Sato, T. Shoji
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2009, 131(1): 011404.
https://doi.org/10.1115/1.3027458
Published Online: November 26, 2008
View Article titled, Quantitative Estimation of the Growth of Environmentally Assisted Cracks at Flaws in Light Water Reactor Components
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Topics: Fracture (Materials), Light water reactors, Stress
Journal Articles

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

Makoto Higuchi, Katsumi Sakaguchi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2007, 129(1): 186–194.
https://doi.org/10.1115/1.2409316
Published Online: June 1, 2006
View Article titled, Review and Consideration of Unsettled Problems on Evaluation of Fatigue Damage in LWR Water
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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

Unified Interpretation of Crack Growth Rates of Ni-base Alloys in LWR Environments

Zhanpeng Lu, Tetsuo Shoji
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2006, 128(3): 318–327.
https://doi.org/10.1115/1.2217964
Published Online: August 8, 2005
View Article titled, Unified Interpretation of Crack Growth Rates of Ni-base Alloys in LWR Environments
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Topics: Alloys, Fracture (Materials), Pressurized water reactors, Nickel, Oxidation, Yield strength, Light water reactors
Journal Articles

Revised Proposal of Fatigue Life Correction Factor F en for Carbon and Low Alloy Steels in LWR Water Environments

Makoto Higuchi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 2004, 126(4): 438–444.
https://doi.org/10.1115/1.1767860
Published Online: December 1, 2004
View Article titled, Revised Proposal of Fatigue Life Correction Factor F en for Carbon and Low Alloy Steels in LWR Water Environments
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Topics: Alloy steel, Carbon, Fatigue, Fatigue life, Oxygen, Sulfur, Temperature, Water, Carbon steel, Light water reactors
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

Technical Basis for the Extension of ASME Code Case N-494 for Assessment of Austenitic Piping

J. M. Bloom
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1996, 118(4): 513–516.
https://doi.org/10.1115/1.2842223
Published Online: November 1, 1996
View Article titled, Technical Basis for the Extension of ASME Code Case N-494 for Assessment of Austenitic Piping
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Topics: ASME Standards, Pipes, Failure, Light water reactors, Stress-strain curves, Cylinders, Stress, Tension, ASME Boiler and Pressure Vessel Code, Deformation
Journal Articles

A Regulatory Perspective on Appropriate Seismic Loading Stress Criteria for Advanced Light Water Reactor Piping Systems

D. Terao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1995, 117(2): 177–181.
https://doi.org/10.1115/1.2842107
Published Online: May 1, 1995
View Article titled, A Regulatory Perspective on Appropriate Seismic Loading Stress Criteria for Advanced Light Water Reactor Piping Systems
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Topics: Light water reactors, Piping systems, Stress
Journal Articles

Rupture Hardware Minimization in Pressurized Water Reactor Piping

S. K. Mukherjee, J. J. Szy Slow Ski, V. Chexal, D. M. Norris, N. A. Goldstein, B. F. Beaudoin, D. F. Quiñones, W. L. Server
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1989, 111(1): 64–71.
https://doi.org/10.1115/1.3265641
Published Online: February 1, 1989
View Article titled, Rupture Hardware Minimization in Pressurized Water Reactor Piping
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Topics: Hardware, Pipes, Pressurized water reactors, Rupture, Containment, Stainless steel, Steel, Construction, Failure, Fatigue cracks
Journal Articles

Status of Research on Environmentally Assisted Cracking in LWR Pressure Vessel Steels

F. P. Ford
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1988, 110(2): 113–128.
https://doi.org/10.1115/1.3265576
Published Online: May 1, 1988
View Article titled, Status of Research on Environmentally Assisted Cracking in LWR Pressure Vessel Steels
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Topics: Cracking (Materials), Fracture (Process), Light water reactors, Pressure vessels, Steel, Fracture (Materials), Alloys, Chemical kinetics, Crack propagation, Rupture
Journal Articles

Performance and Evaluation of Light Water Reactor Pressure Vessels (ASME Special Publication PVP-Vol. 119)

Ravi Rungta, Reviewer, Joe D. Gilman, Reviewer, Warren H. Bamford, Reviewer
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Book Reviews
J. Pressure Vessel Technol. November 1987, 109(4): 473.
https://doi.org/10.1115/1.3264940
Published Online: November 1, 1987
View Article titled, Performance and Evaluation of Light Water Reactor Pressure Vessels (ASME Special Publication PVP-Vol. 119)
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Topics: Light water reactors, Pressure vessels
Journal Articles

Further Development of a Model for Predicting Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels

J. D. Gilman
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 1987, 109(3): 340–346.
https://doi.org/10.1115/1.3264875
Published Online: August 1, 1987
View Article titled, Further Development of a Model for Predicting Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels
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Topics: Corrosion, Fatigue cracks, Reactor vessels, Steel, Fracture (Materials), Stress, Alloys, ASME Standards, Fatigue analysis, Light water reactors
Journal Articles

Evaluation of Flaws in Austenitic Steel Piping

Section XI Task Group for Piping Flaw Evaluation, ASME Code
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Pressure Vessel And Piping Codes
J. Pressure Vessel Technol. August 1986, 108(3): 352–366.
https://doi.org/10.1115/1.3264797
Published Online: August 1, 1986
View Article titled, Evaluation of Flaws in Austenitic Steel Piping
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Topics: Pipes, Steel, Fracture (Materials), Light water reactors, Stress, Welded joints, Acceptance criteria, ASME Boiler and Pressure Vessel Code, Base metals, Emergencies