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O. K. Chopra
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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 Austenitic Stainless Steel Welds 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): 040802.
Paper No: PVT-15-1166
https://doi.org/10.1115/1.4031910
Published Online: April 28, 2016
View Article titled, Methodology for Estimating Thermal and Neutron Embrittlement of Austenitic Stainless Steel Welds During Service in Light Water Reactors
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Topics: Embrittlement, Ferrites (Magnetic materials), Fracture toughness, Welded joints, Neutrons, Temperature
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
Open the PDF for Methodology for Estimating Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels During Service in Light Water Reactors in another window
Topics: Embrittlement, Ferrites (Magnetic materials), Fracture toughness, Neutrons, Temperature, Light water reactors
Proceedings Papers

Statistical Initiation and Crack Growth Models for Stress Corrosion Cracking

W. J. Shack, O. K. Chopra
Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 337-344, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26731
https://doi.org/10.1115/PVP2007-26731
View Paper titled, Statistical Initiation and Crack Growth Models for Stress Corrosion Cracking
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Topics: Fracture (Materials), Stress corrosion cracking, Failure, Statistical distributions, Cracking (Materials), Fracture (Process), Boiling water reactors, Fracture mechanics, Pipes
Proceedings Papers

Crack Growth Behavior of Nickel Alloy Welds in a PWR Environment

B. Alexandreanu, O. K. Chopra, W. J. Shack
Proc. ASME. PVP2007, Volume 1: Codes and Standards, 201-212, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26356
https://doi.org/10.1115/PVP2007-26356
View Paper titled, Crack Growth Behavior of Nickel Alloy Welds in a PWR Environment
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Topics: Fracture (Materials), Nickel alloys, Pressurized water reactors, Welded joints, Cracking (Materials), Fracture (Process), Fatigue, Light water reactors, Coolants, Corrosion
Proceedings Papers

Crack Growth Rates of Irradiated Austenitic Stainless Steels in BWR Environments at 289°C

O. K. Chopra, E. E. Gruber, B. Alexandreanu, Y. Chen, W. J. Shack
Proc. ASME. PVP2007, Volume 1: Codes and Standards, 253-268, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26659
https://doi.org/10.1115/PVP2007-26659
View Paper titled, Crack Growth Rates of Irradiated Austenitic Stainless Steels in BWR Environments at 289°C
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Topics: Boiling water reactors, Fracture (Materials), Stainless steel, Stress, Heat, Irradiation (Radiation exposure), Steel, Tension, Water chemistry
Proceedings Papers

The Stress Corrosion Cracking Behavior of Alloys 690 and 152 Weld in a PWR Environment

B. Alexandreanu, O. K. Chopra, W. J. Shack
Proc. ASME. PVP2008, Volume 1: Codes and Standards, 153-163, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61137
https://doi.org/10.1115/PVP2008-61137
View Paper titled, The Stress Corrosion Cracking Behavior of Alloys 690 and 152 Weld in a PWR Environment
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Topics: Alloys, Pressurized water reactors, Stress corrosion cracking, Fracture (Materials), Fracture (Process), Water, Fatigue, Stress, Temperature, Tensile strength
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
Proceedings Papers

Margins for ASME Code Fatigue Design Curve: Effects of Surface Finish and Material Variability

O. K. Chopra, W. J. Shack
Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 71-85, July 20–24, 2003
Publisher: American Society of Mechanical Engineers
Paper No: PVP2003-1772
https://doi.org/10.1115/PVP2003-1772
View Paper titled, Margins for ASME Code Fatigue Design Curve: Effects of Surface Finish and Material Variability
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Topics: ASME Standards, Fatigue design, Finishes, Fatigue, Light water reactors, Steel, Coolants, Alloys, ASME Boiler and Pressure Vessel Code, Carbon
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

Representation of Elevated-Temperature Tensile Behavior of Type 304 Stainless Steel in a Sodium Environment

O. K. Chopra, K. Natesan
Journal: Journal of Engineering Materials and Technology
Publisher: ASME
Article Type: Research Papers
J. Eng. Mater. Technol. October 1977, 99(4): 366–371.
https://doi.org/10.1115/1.3443553
Published Online: October 1, 1977
View Article titled, Representation of Elevated-Temperature Tensile Behavior of Type 304 Stainless Steel in a Sodium Environment
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Topics: Sodium, Stainless steel, Temperature, Flow (Dynamics), Failure, Stress, Carburization, Ductile fracture, Elongation, Fracture (Materials)