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Proceedings Papers

Use of Large Databases to Identify Trends in the Behavior of Ferritic Steels

Mark T. EricksonKirk, MarjorieAnn EricksonKirk, Charles Rose, Xian J. Zhang

Proc. ASME. PVP2009, Volume 3: Design and Analysis, 527-536, July 26–30, 2009

Paper No: PVP2009-77788

DOI: https://doi.org/10.1115/PVP2009-77788

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Topics: Databases, Steel, Electromagnetic scattering, Alloys, Damage, Fracture (Materials), Fracture (Process), Fracture toughness, Hardening, Irradiation (Radiation exposure)

Proceedings Papers

The Sensitivity of Risk-Informed Reactor Structural Integrity Analysis Results to Various Interpretations of Warm Pre-Stress

Mark T. EricksonKirk, Terry L. Dickson

Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 333-339, July 26–30, 2009

Paper No: PVP2009-77127

DOI: https://doi.org/10.1115/PVP2009-77127

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Topics: Risk, Stress, Transients (Dynamics), Fracture (Materials), Fracture (Process), Accidents, Failure, Modeling, Temperature, Vessels

Proceedings Papers

Insights Arising From a Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

MarjorieAnn EricksonKirk, Mark T. EricksonKirk, Stan Rosinski, Jack Spanner

Proc. ASME. PVP2007, Volume 3: Design and Analysis, 301-317, July 22–26, 2007

Paper No: PVP2007-26305

DOI: https://doi.org/10.1115/PVP2007-26305

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Topics: ASME Standards, Fittings, Fracture toughness, Nuclear reactors, Regulations, Steel, Surveillance, Temperature effects

Proceedings Papers

Effect of Embrittlement Trend Curve Model on the Reference Temperature Based Screening Limits for Pressurized Thermal Shock

Mark T. EricksonKirk, Terry L. Dickson

Proc. ASME. PVP2008, Volume 3: Design and Analysis, 377-388, July 27–31, 2008

Paper No: PVP2008-61649

DOI: https://doi.org/10.1115/PVP2008-61649

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Topics: Embrittlement, Temperature, Thermal shock, Damage, Irradiation (Radiation exposure), Computers, Cracking (Materials), Fracture (Process), Fracture mechanics, Fracture toughness

Proceedings Papers

Insights and Observations Arising From Curve-Fitting the Charpy V-Notch and Tensile Data Contained Within the United States’ Light Water Reactor Surveillance Database

Mark T. EricksonKirk, Atif Shaikh, MarjorieAnn EricksonKirk

Proc. ASME. PVP2008, Volume 3: Design and Analysis, 389-396, July 27–31, 2008

Paper No: PVP2008-61650

DOI: https://doi.org/10.1115/PVP2008-61650

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Topics: Curve fitting, Databases, Light water reactors, Surveillance, Damage, Embrittlement, Irradiation (Radiation exposure), Mechanical properties, Nuclear reactors, Reactor vessels

Journal Articles

A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Marjorie Ann EricksonKirk, Mark T. EricksonKirk, Stan Rosinski, Jack Spanner

J. Pressure Vessel Technol. June 2009, 131(3): 031404.

DOI: https://doi.org/10.1115/1.3109987

Published Online: April 17, 2009

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Topics: Databases, Fracture toughness, Steel, Temperature, Temperature effects, Fittings, Shear (Mechanics), Phase transition temperature, Nuclear reactors

Proceedings Papers

Use of a Unified Model for the Fracture Toughness of Ferritic Steels in the Transition and on the Upper Shelf in Fitness-for-Service Assessment and in the Design of Fracture Toughness Experiments

Mark T. EricksonKirk, MarjorieAnn EricksonKirk

Proc. ASME. PVP2006-ICPVT-11, Volume 3: Design and Analysis, 529-533, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93652

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93652

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Topics: Design, Fitness-for-service, Fracture toughness, Steel, Temperature, Fracture (Materials), Uncertainty, Algebra, ASTM International, Electromagnetic scattering

Journal citation

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Use of Large Databases to Identify Trends in the Behavior of Ferritic Steels

The Sensitivity of Risk-Informed Reactor Structural Integrity Analysis Results to Various Interpretations of Warm Pre-Stress

Insights Arising From a Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Effect of Embrittlement Trend Curve Model on the Reference Temperature Based Screening Limits for Pressurized Thermal Shock

Insights and Observations Arising From Curve-Fitting the Charpy V-Notch and Tensile Data Contained Within the United States’ Light Water Reactor Surveillance Database

A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Use of a Unified Model for the Fracture Toughness of Ferritic Steels in the Transition and on the Upper Shelf in Fitness-for-Service Assessment and in the Design of Fracture Toughness Experiments

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Use of Large Databases to Identify Trends in the Behavior of Ferritic Steels

The Sensitivity of Risk-Informed Reactor Structural Integrity Analysis Results to Various Interpretations of Warm Pre-Stress

Insights Arising From a Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Effect of Embrittlement Trend Curve Model on the Reference Temperature Based Screening Limits for Pressurized Thermal Shock

Insights and Observations Arising From Curve-Fitting the Charpy V-Notch and Tensile Data Contained Within the United States’ Light Water Reactor Surveillance Database

A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data

Use of a Unified Model for the Fracture Toughness of Ferritic Steels in the Transition and on the Upper Shelf in Fitness-for-Service Assessment and in the Design of Fracture Toughness Experiments

Journals

Conference Proceedings

eBooks

Resources

Opportunities

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