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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

EAF, Transferability to Operation and Improving Prospects

Jussi Solin, Tommi Seppänen
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A052, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123437
https://doi.org/10.1115/PVP2024-123437
View Paper titled, EAF, Transferability to Operation and Improving Prospects
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Topics: Electric arc furnaces, Fatigue, Pressurized water reactors, Water, Circuits, Coolants, High temperature, Low temperature, Nuclear reactor coolants, Pressure
Proceedings Papers

Risk-Informed Assessment of French Stress Corrosion Cracking Operational Experience Relative to the Fleet of Pressurized Water Reactors in the United States of America

David Rudland, Matthew Leech, Matthew Homiack, Christopher Nellis
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A074, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-121559
https://doi.org/10.1115/PVP2024-121559
View Paper titled, Risk-Informed Assessment of French Stress Corrosion Cracking Operational Experience Relative to the Fleet of Pressurized Water Reactors in the United States of America
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Topics: Fracture mechanics, Pressurized water reactors, Probabilistic risk assessment, Risk, Stress corrosion cracking
Proceedings Papers

Environmental Effect on Fatigue Life of Stainless Steel for Superimposed Waveforms Simulating High-Cycle Thermal Fatigue

Masayuki Kamaya
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A051, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123082
https://doi.org/10.1115/PVP2024-123082
View Paper titled, Environmental Effect on Fatigue Life of Stainless Steel for Superimposed Waveforms Simulating High-Cycle Thermal Fatigue
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Topics: Cycles, Fatigue, Fatigue life, Pressurized water reactors, Stainless steel
Proceedings Papers

Third-Generation Test Facility for Strain-Controlled EAF

Tommi Seppänen, Esko Arilahti, Jouni Alhainen, Juho Juvalainen, Pekka Moilanen, Jussi Solin
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A050, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122459
https://doi.org/10.1115/PVP2024-122459
View Paper titled, Third-Generation Test Facility for Strain-Controlled EAF
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Topics: ASTM International, Bellows (Equipment), Boundary-value problems, Electric arc furnaces, Engineering prototypes, Fatigue, Fatigue testing, Nuclear reactor coolants, Pressurized water reactors, Stress
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

Low Cycle Fatigue of Alloy 690 in the PWR Environment

Kushal Gowda Jayaram, Joseph Huret, Jonathan Quibel, Walter-John Chitty, Gilbert Henaff
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A046, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123298
https://doi.org/10.1115/PVP2024-123298
View Paper titled, Low Cycle Fatigue of Alloy 690 in the PWR Environment
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Topics: Alloys, Fatigue, Low cycle fatigue, Pressurized water reactors
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

Influence of High Temperature Water on AISI 304 and ER 347 Regarding Their Threshold Value

Georg Veile, Michael Grimm, Stefan Weihe, Jürgen Rudolph
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A047, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-121861
https://doi.org/10.1115/PVP2024-121861
View Paper titled, Influence of High Temperature Water on AISI 304 and ER 347 Regarding Their Threshold Value
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Topics: Boiling water reactors, Corrosion, Fatigue, Fatigue testing, High temperature, Pressurized water reactors, Water
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

Ultrasonic Examination of Welds in Cast Austenitic Stainless Steel PWR Reactor Coolant System Piping Welds

John Hayden, Jason Van Velsor
Proc. ASME. PVP2024, Volume 5: Operations, Applications, & Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T09A006, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123346
https://doi.org/10.1115/PVP2024-123346
View Paper titled, Ultrasonic Examination of Welds in Cast Austenitic Stainless Steel PWR Reactor Coolant System Piping Welds
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Topics: Nuclear reactor coolants, Pipes, Pressurized water reactors, Stainless steel, Ultrasonic testing, Welded joints, Embrittlement, Licensing, Casting, Failure mechanisms
Proceedings Papers

A Methodology for Management of the Risk of Stress Corrosion Cracking of Cold Worked Austenitic Stainless Steels in Good Quality Water in Pressurised Water Reactor Plant

Joseph Malin, James Wilson, Timothy Watkins, Timothy Harrison, Benjamin Pellereau
Proc. ASME. PVP2023, Volume 2: Computer Technology & Bolted Joints; Design & Analysis, V002T03A024, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-108378
https://doi.org/10.1115/PVP2023-108378
View Paper titled, A Methodology for Management of the Risk of Stress Corrosion Cracking of Cold Worked Austenitic Stainless Steels in Good Quality Water in Pressurised Water Reactor Plant
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Topics: Risk, Stainless steel, Stress corrosion cracking, Water, Coolants, Circuits, Defense industry, Failure, Hydrogen, In-service inspection
Proceedings Papers

Probabilistic Fracture Mechanics Evaluation of PWR Cast Austenitic Stainless Steel Piping Components – Axial Cracking Methods and Results

Kevin Fuhr, Matt Wolfson, Glenn White, Markus Burkardt, Do Jun Shim
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A053, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107363
https://doi.org/10.1115/PVP2023-107363
View Paper titled, Probabilistic Fracture Mechanics Evaluation of PWR Cast Austenitic Stainless Steel Piping Components – Axial Cracking Methods and Results
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Topics: Cracking (Materials), Fracture (Process), Fracture mechanics, Pipes, Pressurized water reactors, Stainless steel
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

INCEFA-SCALE Project – Overview of the Modelling Plans

Stephan Courtin, Olivier Ancelet, Jack Beswick, Oliver Blakesley, Roman Cicero
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A012, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-101351
https://doi.org/10.1115/PVP2023-101351
View Paper titled, INCEFA-SCALE Project – Overview of the Modelling Plans
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Topics: Data mining, Fatigue, Modeling, Electric arc furnaces, Fatigue damage, Design, Finite element analysis, Nuclear power stations, Numerical analysis, Pressurized water reactors
Proceedings Papers

Microstructure Characterization of EU INCEFA-SCALE 316L Stainless Steel Fatigue Specimens – Mechanistic Understanding

Aleks Vainionpää, Julio Spadotto, Zaiqing Que, Brian Connolly, Alec Mclennan, Sergio Arrieta, Joseph Huret, Thomas Damiani
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A014, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105888
https://doi.org/10.1115/PVP2023-105888
View Paper titled, Microstructure Characterization of EU INCEFA-SCALE 316L Stainless Steel Fatigue Specimens – Mechanistic Understanding
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Topics: Electron microscopy, Fatigue, Finishes, Pressurized water reactors, Stainless steel
Proceedings Papers

Influence of Insensitive Strain Region for Strain Rate on Fatigue Life of Stainless Steel in PWR Primary Water Environment

Masayuki Kamaya
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A015, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105889
https://doi.org/10.1115/PVP2023-105889
View Paper titled, Influence of Insensitive Strain Region for Strain Rate on Fatigue Life of Stainless Steel in PWR Primary Water Environment
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Topics: Fatigue life, Pressurized water reactors, Stainless steel, Water
Proceedings Papers

Probabilistic Fracture Mechanics Codes for Piping International Benchmark—Part 2: Probabilistic Comparisons

Matthew Homiack, Xinjian Duan, Min Wang, Klaus Heckmann
Proc. ASME. PVP2023, Volume 2: Computer Technology & Bolted Joints; Design & Analysis, V002T03A052, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105733
https://doi.org/10.1115/PVP2023-105733
View Paper titled, Probabilistic Fracture Mechanics Codes for Piping International Benchmark—Part 2: Probabilistic Comparisons
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Topics: Fracture (Materials), Fracture mechanics, Pipes, Probability, Leakage, Leak-before-break, Accounting, Alloys, Corrosion, Electromagnetic scattering
Proceedings Papers

Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach

Fabio Pasti, Sina Tajfirooz, H. J. Uitslag-Doolaard, Francesco Brigante, F. H. E. De Haan-De Wilde
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A029, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105923
https://doi.org/10.1115/PVP2023-105923
View Paper titled, Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach
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Topics: Computational fluid dynamics, Finite element methods, Fracture (Materials), Modeling, Thermal shock, Fracture (Process), Fluids, Simulation, Stress, Brittleness
Proceedings Papers

Experimental Investigation of Combined Axial Flow and Jet Cross-Flow on PWR Mock-Up Array

Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A019, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107312
https://doi.org/10.1115/PVP2023-107312
View Paper titled, Experimental Investigation of Combined Axial Flow and Jet Cross-Flow on PWR Mock-Up Array
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Topics: Axial flow, Cross-flow, Fuel rods, Jets, Pressurized water reactors, Stability