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Proceedings Papers

Technical Basis Document for Alloy 82/182 Weld Inspection Code Case N-770 Through N-770-6

Paul Donavin, Warren Bamford, Stephen Marlette

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A007, July 14–19, 2019

Paper No: PVP2019-94080

DOI: https://doi.org/10.1115/PVP2019-94080

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Topics: Alloys, Inspection, Maintenance, Stress corrosion cracking, Water

Proceedings Papers

Rules for Flaw Interaction for Subsurface Flaws in Operating Pressurized Vessels: Technical Basis of Code Case N-877

Valéry Lacroix, Pierre Dulieu, Sebastien Blasset, Ralf Tiete, Yinsheng Li, Kunio Hasegawa, Warren Bamford, Anees Udyawar

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A048, July 15–20, 2018

Paper No: PVP2018-84120

DOI: https://doi.org/10.1115/PVP2018-84120

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Topics: ASME Standards, Finite element methods, Finite element model, Fitness-for-service, Inspection, Pressure, Pressure vessels, Sensitivity analysis, Vessels

Proceedings Papers

ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation)

Anees Udyawar, Charles Tomes, Alexandria Carolan, Steve Marlette, Thomas Meikle, Warren Bamford

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A020, July 15–20, 2018

Paper No: PVP2018-84346

DOI: https://doi.org/10.1115/PVP2018-84346

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Topics: Licensing, Piping systems, Pressurized water reactors, Fatigue, Transients (Dynamics), Cycles, In-service inspection, Inspection, Construction, Design

Proceedings Papers

Technical Basis for Stress Levels Needed to Mitigate PWSCC in Alloy 82/182/600

Warren Bamford, Glenn White, Stephen Fyfitch

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A047, July 17–21, 2016

Paper No: PVP2016-64041

DOI: https://doi.org/10.1115/PVP2016-64041

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Topics: Indium alloys, Stress, Stress corrosion cracking, Alloys, Cracking (Materials), Fracture (Process), Nickel

Proceedings Papers

Technical Basis for a Flaw Tolerance Option for Code Case N-770-1 for Large Diameter Cold Leg Piping to Main Coolant Pump Welds, With Obstructions

Warren Bamford, Reddy Ganta, Gordon Hall, Matthew Kelley

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 39-49, July 18–22, 2010

Paper No: PVP2010-25145

DOI: https://doi.org/10.1115/PVP2010-25145

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Topics: Coolants, Pipes, Pumps, Welded joints, Inspection, Nozzles, Alloys, ASME Standards, Defense industry, Fracture (Materials)

Proceedings Papers

Technical Basis for Revisions to Section XI Appendix C for Alloy 600/82/182/132 Flaw Evaluation in Both PWR and BWR Environments

Warren Bamford, Russell Cipolla, David Rudland, Guy De Boo

Proc. ASME. PVP2008, Volume 1: Codes and Standards, 343-361, July 27–31, 2008

Paper No: PVP2008-61840

DOI: https://doi.org/10.1115/PVP2008-61840

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Topics: Alloys, Boiling water reactors, Pressurized water reactors, Base metals, Fatigue, Stress, Stress corrosion cracking, Welded joints

Proceedings Papers

Manufacturing Methodology, Repair History, and Loadings for Westinghouse and Combustion Engineering Pressurizers, to Support Detailed Structural Integrity Evaluations of the Nozzle Safe End Configurations

Cameron Martin, Warren Bamford, Nathan Palm

Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 1169-1186, July 27–31, 2008

Paper No: PVP2008-61843

DOI: https://doi.org/10.1115/PVP2008-61843

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Topics: Combustion engineering, Maintenance, Manufacturing, Nozzles, Alloys, Cracking (Materials), Fracture (Process), In-service inspection, Metals, Nuclear power stations

Proceedings Papers

A Review of Alloy 600 Cracking in Operating Nuclear Plants Including Alloy 82 and 182 Weld Behavior

Warren Bamford, John Hall

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 131-139, April 25–29, 2004

Paper No: ICONE12-49520

DOI: https://doi.org/10.1115/ICONE12-49520

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Topics: Alloys, Cracking (Materials), Fracture (Process), Nuclear power stations, Base metals, Fracture (Materials), Pipes, Boilers, Metals, Reactor vessels

Proceedings Papers

Section XI: Responding to Inservice Inspection Findings

Warren Bamford

Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 281, July 20–24, 2003

Paper No: PVP2003-1803

DOI: https://doi.org/10.1115/PVP2003-1803

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Topics: Acceptance criteria, Cracking (Materials), Design, Fracture (Process), In-service inspection, Pipes, Pressurized water reactors, Reactor vessels, Stress corrosion cracking, Vessels

Proceedings Papers

Background and Technical Basis for the Evaluation of Flaws in PWR Reactor Vessel Head Penetration Regions

Warren Bamford, Guy De Boo

Proc. ASME. PVP2004, Pressure Vessel and Piping Codes and Standards, 313-333, July 25–29, 2004

Paper No: PVP2004-2709

DOI: https://doi.org/10.1115/PVP2004-2709

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Topics: Pressurized water reactors, Reactor vessels, Acceptance criteria, Inspection, Leakage, Fracture (Materials), Fracture (Process), Geometry, Plant design, Shapes

Proceedings Papers

Technical Basis for Revision of Inspection Requirements for Regenerative and Residual Heat Exchangers

Warren Bamford, Bruce Bishop, Richard Haessler, Mark Bowler

Proc. ASME. PVP2006-ICPVT-11, Volume 1: Codes and Standards, 77-89, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93892

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93892

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Topics: Heat exchangers, Inspection, Construction, Cycles, In-service inspection, Irradiation (Radiation exposure), Nuclear power stations, Nuclear reactor coolants, Optical quality control, Pressurized water reactors

Proceedings Papers

Recent Experience With Weld Overlay Repair of Indications in Alloy 182 Butt Welds in Two Operating PWRs

Warren Bamford, Bruce Newton, Don Seeger

Proc. ASME. PVP2006-ICPVT-11, Volume 6: Materials and Fabrication, 427-434, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93891

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93891

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Topics: Indium alloys, Maintenance, Overlays (Materials engineering), Pressurized water reactors, Welded joints, Cracking (Materials), Fracture (Process), Inspection, Alloys, Design

Journal citation

NARROW

Technical Basis Document for Alloy 82/182 Weld Inspection Code Case N-770 Through N-770-6

Rules for Flaw Interaction for Subsurface Flaws in Operating Pressurized Vessels: Technical Basis of Code Case N-877

ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation)

Technical Basis for Stress Levels Needed to Mitigate PWSCC in Alloy 82/182/600

Technical Basis for a Flaw Tolerance Option for Code Case N-770-1 for Large Diameter Cold Leg Piping to Main Coolant Pump Welds, With Obstructions

Technical Basis for Revisions to Section XI Appendix C for Alloy 600/82/182/132 Flaw Evaluation in Both PWR and BWR Environments

Manufacturing Methodology, Repair History, and Loadings for Westinghouse and Combustion Engineering Pressurizers, to Support Detailed Structural Integrity Evaluations of the Nozzle Safe End Configurations

A Review of Alloy 600 Cracking in Operating Nuclear Plants Including Alloy 82 and 182 Weld Behavior

Section XI: Responding to Inservice Inspection Findings

Background and Technical Basis for the Evaluation of Flaws in PWR Reactor Vessel Head Penetration Regions

Technical Basis for Revision of Inspection Requirements for Regenerative and Residual Heat Exchangers

Recent Experience With Weld Overlay Repair of Indications in Alloy 182 Butt Welds in Two Operating PWRs

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