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Ernest D. Eason
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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
Open the PDF for 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 in another window
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
Open the PDF for 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 in another window
Topics: Calibration, Heat, Modeling, Stainless steel, Stress corrosion cracking, Fracture (Materials), Yield stress, Irradiation (Radiation exposure), Light water reactors, Fittings
Proceedings Papers

Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments

Ernest D. Eason, Raj Pathania
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A075, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45323
https://doi.org/10.1115/PVP2015-45323
View Paper titled, Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments
Open the PDF for Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments in another window
Topics: Irradiation (Radiation exposure), Light water reactors, Stainless steel, Stress corrosion cracking, Boiling water reactors, Fittings, Fracture (Materials), Pressurized water reactors, Water chemistry, ASME Standards
Proceedings Papers

Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments

Ernest D. Eason, Edward E. Nelson, Graham B. Heys
Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 123-134, July 20–24, 2003
Publisher: American Society of Mechanical Engineers
Paper No: PVP2003-1776
https://doi.org/10.1115/PVP2003-1776
View Paper titled, Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments
Open the PDF for Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments in another window
Topics: Fatigue cracks, Pressurized water reactors, Steel, Sulfur, Water, Databases, Cracking (Materials), Fracture (Materials), Fracture (Process), Pressure vessels
Journal Articles

Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments

Ernest D. Eason, Edward E. Nelson, Graham B. Heys
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. November 2003, 125(4): 385–392.
https://doi.org/10.1115/1.1613948
Published Online: November 4, 2003
View Article titled, Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments
Open the PDF for Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments in another window
Topics: Databases, Fracture (Materials), Pressurized water reactors, Steel, Sulfur, Water, Fatigue cracks