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Proceedings Papers

Present Status of the FRACTESUS Project: Numerical and Experimental Round Robins on Irradiated and Unirradiated Materials

Giovanni Bonny, Inge Uytdenhouwen, Eberhard Altstadt, Pentti Arffman, Sergio Cicero, Florian Obermeier, Tom Petit, Pierrick François, Benoît Tanguy, Helen Swan, Hannah Wilcox
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A057, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122258
https://doi.org/10.1115/PVP2024-122258
View Paper titled, Present Status of the FRACTESUS Project: Numerical and Experimental Round Robins on Irradiated and Unirradiated Materials
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Topics: Finite element analysis, Fracture toughness, Modeling, Reactor vessels, Temperature, Tension
Proceedings Papers

Simulation of Crack Growth in Mini-C(T) Fracture Tests in the Ductile-to-Brittle Transition Using a Cohesive Zone Model: Application to Reactor Pressure Vessel Steels

Audrey Somera, Frédéric Perales, Pierre-Guy Vincent
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A056, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-121961
https://doi.org/10.1115/PVP2024-121961
View Paper titled, Simulation of Crack Growth in Mini-C(T) Fracture Tests in the Ductile-to-Brittle Transition Using a Cohesive Zone Model: Application to Reactor Pressure Vessel Steels
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Topics: Brittleness, Fracture (Materials), Reactor vessels, Simulation, Steel, Fracture toughness, Probability, Temperature, Engineering simulation, Calibration
Proceedings Papers

Technical Basis for Inspection Optimization and Deferral of PWR Pressurizer Component Examinations

Nathaniel G. Cofie, Dilip Dedhia, Scott T. Chesworth, Do Jun Shim, Robert Grizzi
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A076, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-124330
https://doi.org/10.1115/PVP2024-124330
View Paper titled, Technical Basis for Inspection Optimization and Deferral of PWR Pressurizer Component Examinations
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Topics: Inspection, Optimization, Pressurized water reactors, Welded joints, ASME Standards, Vessels, Fracture mechanics, Nozzles, Pressure, Reactor vessels
Proceedings Papers

Biaxial Constraint Effect on Fracture Toughness Evaluation of Reactor Pressure Vessel Under Pressurized Thermal Shock Events

Masaki Shimodaira, Yoshihito Yamaguchi, Keiko Iwata, Jinya Katsuyama, Yasuhiro Chimi
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A065, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123136
https://doi.org/10.1115/PVP2024-123136
View Paper titled, Biaxial Constraint Effect on Fracture Toughness Evaluation of Reactor Pressure Vessel Under Pressurized Thermal Shock Events
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Topics: Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Thermal shock
Proceedings Papers

Project FRACTESUS: Fracture Toughness Round Robin on a High Copper Weld Using Miniature C(T) Specimens – Results and Discussion

Florian Obermeier, Inge Uytdenhouwen, Eberhard Altstadt, Sergio Cicero, Marcos Sánchez, John Echols, Giovanni Bonny
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A061, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122646
https://doi.org/10.1115/PVP2024-122646
View Paper titled, Project FRACTESUS: Fracture Toughness Round Robin on a High Copper Weld Using Miniature C(T) Specimens – Results and Discussion
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Topics: Copper, Fracture toughness, Finite element model, Irradiation (Radiation exposure), Pressurized water reactors, Testing, ASTM International, Brittleness, Embrittlement, Heat
Proceedings Papers

Ultrasonic Testing in Lieu of Radiographic Testing: Application to ASME III Class 1 Nuclear Pressure Vessels in the Context of Rolls-Royce Structural Justification Expectations

David Whitehead, David Rice
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A001, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-121384
https://doi.org/10.1115/PVP2024-121384
View Paper titled, Ultrasonic Testing in Lieu of Radiographic Testing: Application to ASME III Class 1 Nuclear Pressure Vessels in the Context of Rolls-Royce Structural Justification Expectations
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Topics: Reactor vessels, Testing, Ultrasonic testing
Proceedings Papers

Plastic Constraint Correction Factor X for Brittle Fracture in Ductile-Brittle Transition Temperature Region

Kiminobu Hojo, Takatoshi Hirota, Yasuto Nagoshi, Takuya Fukahori, Kazuma Shimizu, Masaki Shimodaira, Takuya Ogawa, Kenji Yashirodai, Mitsuru Ohata, Fumiyoshi Minami
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A066, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123140
https://doi.org/10.1115/PVP2024-123140
View Paper titled, Plastic Constraint Correction Factor X for Brittle Fracture in Ductile-Brittle Transition Temperature Region
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Topics: Brittle fracture, Ductile-brittle transition, Fracture (Materials), Fracture (Process), Temperature, Reactor vessels, Shapes, Yield strength, Ductile fracture, Geometry
Proceedings Papers

Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique – Evaluation of Results

Florian Obermeier, Eberhard Altstadt, Hieronymus Hein, Aniruddh Das, Johannes May
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A059, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122615
https://doi.org/10.1115/PVP2024-122615
View Paper titled, Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique – Evaluation of Results
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Topics: Fracture toughness, Steel, Fracture mechanics, Surveillance, Testing, Displacement, ASTM International, Cracking (Materials), Economics , Embrittlement
Proceedings Papers

Validity of Toughness Measurements From Miniature Specimens Failing in Different Fracture Modes

Susan Ortner, Marcos Sanchez, John Echols, Sergio Cicero, Paul Chekhonin
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A062, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122781
https://doi.org/10.1115/PVP2024-122781
View Paper titled, Validity of Toughness Measurements From Miniature Specimens Failing in Different Fracture Modes
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Topics: Brittle fracture, Fractography, Fracture (Materials), Fracture (Process), Fracture toughness, Reactor vessels, Tension
Proceedings Papers

Investigation Into the Effects of Cladding in Thermal Fatigue Evaluations of Nuclear Pressure Vessels and Components

Ben Pellereau, Meyrick Hockly, Wolf Reinhardt
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A049, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123541
https://doi.org/10.1115/PVP2024-123541
View Paper titled, Investigation Into the Effects of Cladding in Thermal Fatigue Evaluations of Nuclear Pressure Vessels and Components
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Topics: Cladding systems (Building), Fatigue, Reactor vessels
Proceedings Papers

XFEM Simulation and Parametric Analysis of Thick-Walled Cylindrical Mock-Ups Under Thermo-Shock

Diego Fernando Mora Mendez, Markus Niffenegger
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A088, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122127
https://doi.org/10.1115/PVP2024-122127
View Paper titled, XFEM Simulation and Parametric Analysis of Thick-Walled Cylindrical Mock-Ups Under Thermo-Shock
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Topics: Fracture (Materials), Shock (Mechanics), Simulation, Cooling, Loss of coolant accidents, Safety, Crack propagation, Finite element model, Hoop stress, Nuclear power
Proceedings Papers

Full Scale Three-Dimensional Moving Arc Weld Analyses of Control Rod Drive Mechanism J-Groove Welds and Implications on Cracking

Frederick W. Brust, Ed Punch, Elizabeth Twombly
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A026, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-125081
https://doi.org/10.1115/PVP2024-125081
View Paper titled, Full Scale Three-Dimensional Moving Arc Weld Analyses of Control Rod Drive Mechanism J-Groove Welds and Implications on Cracking
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Topics: Cracking (Materials), Fracture (Process), Welded joints, Nozzles, Fracture (Materials), Pressurized water reactors, Metals, Stress corrosion cracking, Water, Alloys
Proceedings Papers

Fitness-for-Service Analysis of a Light Water Reactor Pressure Vessel Under Complex Operating Conditions

Minh N. Tran, Ondrej Muransky, Benjamin W. Spencer
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A032, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-121895
https://doi.org/10.1115/PVP2024-121895
View Paper titled, Fitness-for-Service Analysis of a Light Water Reactor Pressure Vessel Under Complex Operating Conditions
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Topics: Finite element analysis, Fitness-for-service, Light water reactors, Pressure vessels, Stress, Energy generation, Thermomechanics, Transients (Dynamics), ASME Boiler and Pressure Vessel Code, Computer simulation
Proceedings Papers

Residual Stress Modelling in PWR Reactor Pressure Vessel Welded Joints

Vincent Robin, Lucas Breder Teixeira, David Albrecht, Sofiane Hendili, Sami Hilal, Pablo Pereira Alvarez, Josselin Delmas, Lionel Depradeux, Mike C. Smith, Anastasia Vasileiou
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A024, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123470
https://doi.org/10.1115/PVP2024-123470
View Paper titled, Residual Stress Modelling in PWR Reactor Pressure Vessel Welded Joints
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Topics: Modeling, Pressurized water reactors, Reactor vessels, Stress, Welded joints, Welding
Proceedings Papers

Technical Basis for Inspection Optimization and Deferral of PWR Steam Generator Component Examinations

Nathaniel G. Cofie, Dilip Dedhia, Scott T. Chesworth, Do Jun Shim, Robert Grizzi
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A052, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105958
https://doi.org/10.1115/PVP2023-105958
View Paper titled, Technical Basis for Inspection Optimization and Deferral of PWR Steam Generator Component Examinations
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Topics: Boilers, Inspection, Optimization, Pressurized water reactors, ASME Standards, Pressure, Welded joints, Nozzles, Pressure vessels, Vessels
Proceedings Papers

Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens

Timo Metzler, Ermile Gaganidze, Jarir Aktaa
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A034, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105918
https://doi.org/10.1115/PVP2023-105918
View Paper titled, Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens
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Topics: Fracture toughness, Reactor vessels, Steel
Proceedings Papers

Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management

Mark Kirk, Marjorie Erickson, Elliot J. Long
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A033, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105904
https://doi.org/10.1115/PVP2023-105904
View Paper titled, Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management
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Topics: ASME Standards, Base metals, Electromagnetic scattering, Embrittlement, Fracture toughness, Heat, Irradiation (Radiation exposure), Metals, Neutrons, Phase transition temperature
Proceedings Papers

Test Temperature Selection Procedures for Small Specimen Master Curve Tests Considering the Possibility of Inhomogeneous Materials

Masato Yamamoto, Mark Kirk
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A026, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-101326
https://doi.org/10.1115/PVP2023-101326
View Paper titled, Test Temperature Selection Procedures for Small Specimen Master Curve Tests Considering the Possibility of Inhomogeneous Materials
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Topics: Fracture toughness, Temperature, ASTM International, Deformation, Reactor vessels, Steel, Weibull distribution, Yield stress
Proceedings Papers

Present Status of the Fractesus Project: Round Robin on Unirradiated Materials

G. Bonny, E. Altstadt, P. Arffman, S. Cicero, F. Obermeier, T. Petit, H. Swan, R. Chaouadi, E. Gaganidze, B. Hargitai, M. Kolluri, R. Kopriva, P. Rozsahegyi, M. Serrano, P. Spätig, I. Uytdenhouwen, H. Wilcox, M. Yamamoto
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A030, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105449
https://doi.org/10.1115/PVP2023-105449
View Paper titled, Present Status of the Fractesus Project: Round Robin on Unirradiated Materials
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Topics: Computer software, Displacement, Fracture toughness, Reactor vessels, Stress, Temperature, Tension, Testing, Welded joints
Proceedings Papers

Technical Basis for Revision to Code Case N-702

Matthew Walter, Kevin Wong, Nathaniel G. Cofie, Mo Uddin, Gary Dominguez
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A004, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107044
https://doi.org/10.1115/PVP2023-107044
View Paper titled, Technical Basis for Revision to Code Case N-702
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Topics: Acceptance criteria, ASME Standards, Boiling water reactors, Engineering standards, Failure, Feedwater, Fracture mechanics, In-service inspection, Inspection, Nozzles