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Proceedings Papers

INCEFA-SCALE Project – Phases 1 and 2 of Testing Programme

Jack Beswick, Luc Doremus, Oliver Martin, Jean-Christophe Le Roux
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A010, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-106243
https://doi.org/10.1115/PVP2023-106243
View Paper titled, INCEFA-SCALE Project – Phases 1 and 2 of Testing Programme
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Topics: Fatigue, Pressurized water reactors, Testing
Proceedings Papers

Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components

Timothy G. Lach, Xiang (Frank) Chen
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A063, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107347
https://doi.org/10.1115/PVP2023-107347
View Paper titled, Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components
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Topics: Irradiation (Radiation exposure), Nuclear reactors, Pressurized water reactors, Stainless steel
Proceedings Papers

Development of Prediction Tool for Flow-Accelerated Corrosion (4) Development and Validation of Prediction Software “FALSET” With Water Single-Phase FAC Data Obtained in Japanese PWR Plants

Ryo Morita, Yuta Uchiyama, Kazutoshi Fujiwara, Kimitoshi Yoneda
Proc. ASME. PVP2023, Volume 6: Operations, Applications, & Components, V006T07A009, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105766
https://doi.org/10.1115/PVP2023-105766
View Paper titled, Development of Prediction Tool for Flow-Accelerated Corrosion (4) Development and Validation of Prediction Software “FALSET” With Water Single-Phase FAC Data Obtained in Japanese PWR Plants
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Topics: Computer software, Corrosion, Flow (Dynamics), Pressurized water reactors, Water, Pipes, Power stations, Wall thickness, Maintenance, Public utilities
Proceedings Papers

Evaluation of the Inherent LBB Behavior of Small-Diameter Class 1 and 2 Nuclear Piping Systems

Elizabeth Twombly, Lance Hill, Gery Wilkowski, Frederick Brust, Bruce Lin, Robert Tregoning
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A042, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107685
https://doi.org/10.1115/PVP2023-107685
View Paper titled, Evaluation of the Inherent LBB Behavior of Small-Diameter Class 1 and 2 Nuclear Piping Systems
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Topics: Leak-before-break, Pipes, Piping systems, Stress, Displacement, Fracture (Materials), Plasticity, Boiling water reactors, Design, Pressurized water reactors
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

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

Study on Analysis Procedure Using Integrated Three-Dimensional FE Model for Reactor Coolant System by Applying to Shaking Table Tests for Scaled Mock-Ups

Takehiro Kawashima, Yasutaka Kumagai, Yuki Asao, Shota Shimazu, Takuya Nishimura
Proc. ASME. PVP2023, Volume 7: Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V007T08A019, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107126
https://doi.org/10.1115/PVP2023-107126
View Paper titled, Study on Analysis Procedure Using Integrated Three-Dimensional FE Model for Reactor Coolant System by Applying to Shaking Table Tests for Scaled Mock-Ups
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Topics: Finite element model, Nuclear reactor coolants, Stress, Finite element analysis, Reactor vessels, Stress analysis (Engineering), Computers, Evaluation methods, Nuclear power stations, Pressurized water reactors
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
Proceedings Papers

The Development of a New Method to Compare the Fatigue Crack Growth Rates of Austenitic Stainless Steel Operating in a PWR Primary Coolant Subjected to Plant Realistic Temperature Loading

Benjamin Howe, Fabio Scenini, Grace Burke, Jonathan Mann
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A011, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84208
https://doi.org/10.1115/PVP2022-84208
View Paper titled, The Development of a New Method to Compare the Fatigue Crack Growth Rates of Austenitic Stainless Steel Operating in a PWR Primary Coolant Subjected to Plant Realistic Temperature Loading
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Topics: Coolants, Fatigue, Fatigue cracks, Pressurized water reactors, Stainless steel, Temperature
Proceedings Papers

3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds

Pierre Dulieu, Valéry Lacroix
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A036, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84667
https://doi.org/10.1115/PVP2022-84667
View Paper titled, 3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds
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Topics: Metals, Simulation, Stress corrosion cracking, Tolerance analysis, Water, Welded joints, Stress, Fracture (Materials), Accounting, Alloys
Proceedings Papers

Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles

Pierre Dulieu, Valéry Lacroix, Vratislav Mares, Larbi Arbaoui, Jean-Philippe Bournot
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A082, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-79529
https://doi.org/10.1115/PVP2022-79529
View Paper titled, Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles
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Topics: Metals, Nozzles, Reactor vessels, Residual stresses, Stress, Welding, Heat, Simulation, Welded joints, Alloys
Proceedings Papers

Revision of the Annex Z V Concerning the Calculation of Bolted Joints in the French Nuclear Code RCC-M®

Hubert Lejeune, Philippe Rohart, Manuela Triay, Aurélien Di Rienzo
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A014, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-81911
https://doi.org/10.1115/PVP2022-81911
View Paper titled, Revision of the Annex Z V Concerning the Calculation of Bolted Joints in the French Nuclear Code RCC-M®
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Topics: Bolted flanges, Bolted joints, Computational methods, Construction, Design, Electromagnetic scattering, Flanges, Gaskets, Graphite, Manufacturing
Proceedings Papers

An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario

Nicholas Klymyshyn, Kevin Kadooka, Casey Spitz, James Fitzpatrick
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A028, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84353
https://doi.org/10.1115/PVP2022-84353
View Paper titled, An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
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Topics: Spent nuclear fuels, Stress, Fuels, Manufacturing, Damage, Modeling, Boiling water reactors, Boundary element methods, Collaboration, Design
Proceedings Papers

Investigation Into Degradation of a Pilot Operated Pressure Relief Valve Main Seat During Development Testing

Martin Kane, Phil Thompson, David Stewart
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A017, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83156
https://doi.org/10.1115/PVP2022-83156
View Paper titled, Investigation Into Degradation of a Pilot Operated Pressure Relief Valve Main Seat During Development Testing
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Topics: Corrosion, Damage, Relief valves, Testing, Valves, Cobalt alloys, Erosion, Failure, Flow (Dynamics), Leakage