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W. H. Bamford
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Proceedings Papers

Modeling Crack Growth in ASME Section XI Flaw Evaluations

W. H. Bamford, Anees Udyawar
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A003, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-64992
https://doi.org/10.1115/PVP2021-64992
View Paper titled, Modeling Crack Growth in ASME Section XI Flaw Evaluations
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Topics: ASME Standards, Fracture (Materials), Modeling
Proceedings Papers

Flaw Evaluation for PWR and BWR Component Weld Joints Using Advanced FEA Modeling Techniques

T. Hayashi, S. F. Hankinson, T. Saito, C. K. Ng, W. H. Bamford
Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 1125-1139, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77855
https://doi.org/10.1115/PVP2009-77855
View Paper titled, Flaw Evaluation for PWR and BWR Component Weld Joints Using Advanced FEA Modeling Techniques
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Topics: Boiling water reactors, Finite element analysis, Modeling, Pressurized water reactors, Fracture (Materials), Shapes, Crack propagation, Stress corrosion cracking, Geometry, Metals
Proceedings Papers

The Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations and Its Application at North Anna Unit 2

W. H. Bamford, L. L. Spain, R. E. Gold, W. R. Gahwiller, J. P. Lareau
Proc. ASME. PVP2003, Flaw Evaluation, Service Experience, and Reliability, 159-170, July 20–24, 2003
Publisher: American Society of Mechanical Engineers
Paper No: PVP2003-2038
https://doi.org/10.1115/PVP2003-2038
View Paper titled, The Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations and Its Application at North Anna Unit 2
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Topics: Maintenance, Reactor vessels, Cracking (Materials), Fracture (Process), Inspection, Welded joints
Journal Articles

Thermal Aging of Cast Stainless Steel, and Its Impact on Piping Integrity

W. H. Bamford, E. I. Landerman, E. Diaz
Journal: Journal of Engineering Materials and Technology
Publisher: ASME
Article Type: Research Papers
J. Eng. Mater. Technol. January 1985, 107(1): 53–60.
https://doi.org/10.1115/1.3225771
Published Online: January 1, 1985
View Articletitled, Thermal Aging of Cast Stainless Steel, and Its Impact on Piping Integrity
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Topics: Pipes, Stainless steel, Failure mechanisms, Heat, Failure, Ferrites (Magnetic materials), Furnaces, Mechanical properties, Temperature effects
Journal Articles

Technical Basis for Revised Reference Crack Growth Rate Curves for Pressure Boundary Steels in LWR Environment

W. H. Bamford
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Pressure Vessel And Piping Codes
J. Pressure Vessel Technol. November 1980, 102(4): 433–442.
https://doi.org/10.1115/1.3263355
Published Online: November 1, 1980
View Articletitled, Technical Basis for Revised Reference Crack Growth Rate Curves for Pressure Boundary Steels in LWR Environment
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Topics: Fracture (Materials), Light water reactors, Pressure, Steel, Stress, Alloys, Carbon, Coolants, Fatigue cracks, Pressure vessels
Journal Articles

Application of Corrosion Fatigue Crack Growth Rate Data to Integrity Analyses of Nuclear Reactor Vessels

W. H. Bamford
Journal: Journal of Engineering Materials and Technology
Publisher: ASME
Article Type: Research Papers
J. Eng. Mater. Technol. July 1979, 101(3): 182–190.
https://doi.org/10.1115/1.3443676
Published Online: July 1, 1979
View Articletitled, Application of Corrosion Fatigue Crack Growth Rate Data to Integrity Analyses of Nuclear Reactor Vessels
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Topics: Corrosion, Fatigue cracks, Nuclear reactors, Vessels, Fracture (Materials), Water, ASME Standards, Pressure vessels, Steel
Journal Articles

Fatigue Crack Growth of Stainless Steel Piping in a Pressurized Water Reactor Environment

W. H. Bamford
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1979, 101(1): 73–79.
https://doi.org/10.1115/1.3454601
Published Online: February 1, 1979
View Articletitled, Fatigue Crack Growth of Stainless Steel Piping in a Pressurized Water Reactor Environment
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Topics: Fatigue cracks, Pipes, Pressurized water reactors, Stainless steel, Stress, Fracture (Materials), Fatigue, Heat, Base metals, Temperature
Journal Articles

Reactor Coolant Pump Flywheel Overspeed Evaluation

P. C. Riccardella, W. H. Bamford
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1974, 96(4): 279–285.
https://doi.org/10.1115/1.3454182
Published Online: November 1, 1974
View Articletitled, Reactor Coolant Pump Flywheel Overspeed Evaluation
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Topics: Flywheels, Nuclear reactor coolants, Pumps, Fracture mechanics, ASME Boiler and Pressure Vessel Code, Brittle fracture, Computers, Coolants, Design, Engineering prototypes