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Warren H. Bamford
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Proceedings Papers

Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments

Russell C. Cipolla, Warren H. Bamford, Kiminobu Hojo, Yuichiro Nomura
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A001, July 13–15, 2021
Paper No: PVP2021-61728
DOI: https://doi.org/10.1115/PVP2021-61728
View Paper titled, Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
Click here to open pdf in another window PDF for Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
Topics: Fatigue cracks, Pressurized water reactors, Stainless steel
Proceedings Papers

Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds

Amanda Jenks, Warren H. Bamford
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A004, August 3, 2020
Paper No: PVP2020-21711
DOI: https://doi.org/10.1115/PVP2020-21711
View Paper titled, Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds
Click here to open pdf in another window PDF for Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds
Topics: Alloys, Fracture (Materials), Stress corrosion cracking, Welded joints
eBook Chapter

Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation

Series: eBooks
Publisher: ASME Press
Published: 2020
Click here to open pdf in another window PDF for Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation
Topics: Fracture (Materials), Fatigue cracks, Stress
eBook Chapter

Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation

Publisher: ASME Press
Published: 2018
ISBN: 9780791861318
Click here to open pdf in another window PDF for Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation
Topics: Fatigue, Fatigue cracks, Stress corrosion cracking
Proceedings Papers

Technical Basis for Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments

Russell C. Cipolla, Warren H. Bamford
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A010, July 19–23, 2015
Paper No: PVP2015-45884
DOI: https://doi.org/10.1115/PVP2015-45884
View Paper titled, Technical Basis for Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
Click here to open pdf in another window PDF for Technical Basis for Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
Topics: Fatigue cracks, Pressurized water reactors, Stainless steel, Stress, Inspection, Pipes, Service life (Equipment), Temperature
Proceedings Papers

Example Analysis for Environmental Fatigue Crack Growth in Austenitic Stainless Steel Piping Using Code Case N-809

Warren H. Bamford, Russell C. Cipolla, Anees Udyawar, Nathan L. Glunt
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A012, July 19–23, 2015
Paper No: PVP2015-45967
DOI: https://doi.org/10.1115/PVP2015-45967
View Paper titled, Example Analysis for Environmental Fatigue Crack Growth in Austenitic Stainless Steel Piping Using Code Case N-809
Click here to open pdf in another window PDF for Example Analysis for Environmental Fatigue Crack Growth in Austenitic Stainless Steel Piping Using Code Case N-809
Topics: Fatigue cracks, Pipes, Stainless steel, Pressurized water reactors, Stress, Engineering standards, Nuclear reactor coolants, Temperature
Proceedings Papers

Changing the Frequency of Inspections for PWSCC Susceptible Welds at Cold Leg Temperatures

Nathan A. Palm, Warren H. Bamford, Craig Harrington
Proc. ASME. PVP2011, Volume 1: Codes and Standards, 69-83, July 17–21, 2011
Paper No: PVP2011-57829
DOI: https://doi.org/10.1115/PVP2011-57829
View Paper titled, Changing the Frequency of Inspections for PWSCC Susceptible Welds at Cold Leg Temperatures
Click here to open pdf in another window PDF for Changing the Frequency of Inspections for PWSCC Susceptible Welds at Cold Leg Temperatures
Topics: Inspection, Temperature, Welded joints, Pipes, Alloys, Cracking (Materials), Fracture (Materials), Fracture (Process), In-service inspection, Metals
eBook Chapter

Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation

Publisher: ASME Press
Published: 2012
ISBN: 9780791859872
Click here to open pdf in another window PDF for Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation
Topics: Fatigue, Fatigue cracks, Stress corrosion cracking
Proceedings Papers

Technical Basis for Revisions to ASME Section XI Acceptance Standards for Surface Flaws in Piping in Stress Corrosion Cracking Susceptible Materials

Douglas A. Scarth, Katsumasa Miyazaki, Kunio Hasegawa, Warren H. Bamford
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 323-337, July 26–30, 2009
Paper No: PVP2009-77824
DOI: https://doi.org/10.1115/PVP2009-77824
View Paper titled, Technical Basis for Revisions to ASME Section XI Acceptance Standards for Surface Flaws in Piping in Stress Corrosion Cracking Susceptible Materials
Click here to open pdf in another window PDF for Technical Basis for Revisions to ASME Section XI Acceptance Standards for Surface Flaws in Piping in Stress Corrosion Cracking Susceptible Materials
Topics: Acceptance criteria, Pipes, Stress corrosion cracking, Boiling water reactors, Fracture (Materials), Pressurized water reactors, Coolants, Failure, Fatigue, Fatigue cracks
eBook Chapter

Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation

Publisher: ASME Press
Published: 2009
ISBN: 9780791802700
Click here to open pdf in another window PDF for Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation
Topics: Fatigue, Fatigue cracks, Stress corrosion cracking
Proceedings Papers

Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Components in ASME Code Section XI

Russell C. Cipolla, Guy H. DeBoo, Warren H. Bamford, Jr., Kenneth K. Yoon, Kunio K. Hasegawa
Proc. ASME. PVP2003, Flaw Evaluation, Service Experience, and Reliability, 3-18, July 20–24, 2003
Paper No: PVP2003-2022
DOI: https://doi.org/10.1115/PVP2003-2022
View Paper titled, Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Components in ASME Code Section XI
Click here to open pdf in another window PDF for Flaw Evaluation Procedures and Acceptance Criteria for Nuclear Components in ASME Code Section XI
Topics: Acceptance criteria, ASME Standards, Pressure, Leakage, Nuclear power stations, ASME Boiler and Pressure Vessel Code, Failure, In-service inspection, Mechanical engineers, Nuclear reactor coolants
Proceedings Papers

Technical Basis for Acceptance of Flaws in Moderate Energy Class 2 and 3 Vessels and Tanks

Pat L. Strauch, Warren H. Bamford, Jr., Sushil K. Daftuar
Proc. ASME. PVP2004, Pressure Vessel and Piping Codes and Standards, 335-340, July 25–29, 2004
Paper No: PVP2004-2710
DOI: https://doi.org/10.1115/PVP2004-2710
View Paper titled, Technical Basis for Acceptance of Flaws in Moderate Energy Class 2 and 3 Vessels and Tanks
Click here to open pdf in another window PDF for Technical Basis for Acceptance of Flaws in Moderate Energy Class 2 and 3 Vessels and Tanks
Topics: Vessels, Leakage, Inspection, Acceptance criteria, ASME Standards, Failure, Fracture (Materials), Pipes, Stress corrosion cracking, Surveillance
Proceedings Papers

Decision Advisor for Multi-Component Management of Alloy 600 Degradation Issues at the Exelon Braidwood and Byron Nuclear Power Plants

G. Gary Elder, Clark W. Mycoff, Gregory Gerzen, Robert K. Perdue, Edward A. Ray, Warren H. Bamford
Proc. ASME. PVP2005, Volume 7: Operations, Applications, and Components, 117-124, July 17–21, 2005
Paper No: PVP2005-71762
DOI: https://doi.org/10.1115/PVP2005-71762
View Paper titled, Decision Advisor for Multi-Component Management of Alloy 600 Degradation Issues at the Exelon Braidwood and Byron Nuclear Power Plants
Click here to open pdf in another window PDF for Decision Advisor for Multi-Component Management of Alloy 600 Degradation Issues at the Exelon Braidwood and Byron Nuclear Power Plants
Topics: Alloys, Nuclear power stations, Nuclear power
eBook Chapter

Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation

Publisher: ASME Press
Published: 2006
ISBN-10: 0791802191
Click here to open pdf in another window PDF for Fatigue Crack Growth, Fatigue, and Stress Corrosion Crack Growth: Section XI Evaluation
Topics: Fatigue, Fatigue cracks, Stress corrosion cracking
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
Article Type: Book Reviews
J. Pressure Vessel Technol. November 1987, 109(4): 473.
DOI: 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)
Click here to open pdf in another window PDF for Performance and Evaluation of Light Water Reactor Pressure Vessels (ASME Special Publication PVP-Vol. 119)
Topics: Light water reactors, Pressure vessels