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Proceedings Papers

Pilot Study on Seismic Fragility Evaluation for Degraded Austenitic Stainless Steel Piping Using the Probabilistic Fracture Mechanics Code PASCAL-SP

Kisaburo Azuma, Yoshihito Yamaguchi, Yinsheng Li

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A063, July 13–15, 2021

Paper No: PVP2021-62233

DOI: https://doi.org/10.1115/PVP2021-62233

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Topics: Fracture mechanics, Pipes, Stainless steel, Inspection, Maintenance, Stress corrosion cracking, Failure, Probabilistic risk assessment, Probability, Design

Proceedings Papers

Further Development of Probabilistic Leak-Before-Break Methods

Peter Gill, Brian Daniels

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A039, July 13–15, 2021

Paper No: PVP2021-62936

DOI: https://doi.org/10.1115/PVP2021-62936

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Topics: Leak-before-break, Fracture (Materials), Probability, Computer software, Cylinders, Engineering simulation, Failure, Leakage, Pipes, Simulation

Proceedings Papers

Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material

Takahiro Hayashi, Takuya Ogawa, Shuichi Yoshida, Masao Itatani, Yasuhiro Hattori, Tetsushi Yamaoka, Shigeaki Tanaka, Toshiyuki Saito

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A047, July 13–15, 2021

Paper No: PVP2021-61467

DOI: https://doi.org/10.1115/PVP2021-61467

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Topics: Alloy steel, Alloys, Boiling water reactors, Fracture (Materials), Fracture mechanics, Fracture toughness, Metals, Reactor vessels, Stress corrosion cracking

Proceedings Papers

Thermal Stress Analysis of a Spent Nuclear Fuel Canister

Ben J. Jensen, Charlton F. Campbell, Nicholas A. Klymyshyn

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A024, July 13–15, 2021

Paper No: PVP2021-61608

DOI: https://doi.org/10.1115/PVP2021-61608

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Topics: Spent nuclear fuels, Thermal stresses, Stress, Temperature profiles, Computer simulation, Crack propagation, Earthquakes, Finite element analysis, Finite element model, Helium

Proceedings Papers

Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR

Chris Lohse, Do Jun Shim, Dilip Dedhia, Rohan Dutta, Nathan Glunt

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A030, July 13–15, 2021

Paper No: PVP2021-62560

DOI: https://doi.org/10.1115/PVP2021-62560

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Topics: Inspection, Metals, Pressurized water reactors, Welded joints, Fracture (Materials), Alloys, ASME Standards, Computers, Probability, Temperature

Proceedings Papers

Benchmarking Study on Probabilistic Fracture Mechanics Analysis Codes xLPR and PASCAL-SP Considering Primary Water Stress Corrosion Cracking

Akihiro Mano, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A027, July 13–15, 2021

Paper No: PVP2021-61202

DOI: https://doi.org/10.1115/PVP2021-61202

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Topics: Fracture mechanics, Stress corrosion cracking, Water

Proceedings Papers

Technical Basis Summary for Code Case N-860: Inspection Requirements and Evaluation Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems

John E. Broussard, III

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A061, July 13–15, 2021

Paper No: PVP2021-64176

DOI: https://doi.org/10.1115/PVP2021-64176

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Topics: Containment systems, Inspection, Spent fuel storage, Spent nuclear fuels, Stress corrosion cracking, Transportation systems, In-service inspection, Acceptance criteria, ASME Boiler and Pressure Vessel Code, Fracture (Materials)

Proceedings Papers

Stress Analysis of Tubes During Die Expansion Process

Zijian Zhao, Abdel-Hakim Bouzid

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A006, July 13–15, 2021

Paper No: PVP2021-61724

DOI: https://doi.org/10.1115/PVP2021-61724

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Topics: Copper, Experimental methods, Finite element model, Hardening, Kinematics, Leakage, Materials properties, Stainless steel, Stress, Stress analysis (Engineering)

Proceedings Papers

Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking

Stephen Marlette, Steven L. McCraken, Christopher Lohse

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A097, August 3, 2020

Paper No: PVP2020-21544

DOI: https://doi.org/10.1115/PVP2020-21544

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Topics: Fatigue cracks, Maintenance, Pipes, Stainless steel, Overlays (Materials engineering), Fatigue, Boiling water reactors, Pressurized water reactors, Stress corrosion cracking, Design

Proceedings Papers

A Feasibility Study on Crack Repair in Austenitic Stainless Steel Dry Storage Canisters Using Isothermal Friction Stir Welding

Madhumanti Bhattacharyya, Indrajit Charit, Krishnan Raja, Jens Darsell, Saumyadeep Jana

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A099, August 3, 2020

Paper No: PVP2020-21716

DOI: https://doi.org/10.1115/PVP2020-21716

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Topics: Fracture (Materials), Friction, Maintenance, Microhardness, Stainless steel, Storage, Welding, Plates (structures), Base metals, Damage

Proceedings Papers

Deployment of Laser Peening to Prevent CISCC of Nuclear Fuel Dry Storage Canisters

Lloyd Hackel, Jon Rankin, Matt Walter, C. Brent Dane, William Neuman, Pierre Oneid, Gareth Thomas, Fred Bidrawn

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A033, August 3, 2020

Paper No: PVP2020-21045

DOI: https://doi.org/10.1115/PVP2020-21045

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Topics: Alloys, Laser hardening, Nuclear fuels, Spent nuclear fuels, Stainless steel, Storage, Stress corrosion cracking

Proceedings Papers

Tempering Response in Type 410 Stainless Steel Welds for Petrochemical Application

Takuya Kusunoki, Boian Alexandrov, Benjamin Lawson, Jorge Penso, Joe Bundy

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A067, August 3, 2020

Paper No: PVP2020-21753

DOI: https://doi.org/10.1115/PVP2020-21753

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Topics: Petrochemicals, Stainless steel, Welded joints, Temperature, Base metals, Fracture toughness, Metals, Welding, ASME Standards, Ferrites (Magnetic materials)

Proceedings Papers

Impact of Grooves in Hydraulically Expanded Tube-to-Tubesheet Joints

Dinu Thomas Thekkuden, Abdel-Hamid I. Mourad, Abdel-Hakim Bouzid

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A020, August 3, 2020

Paper No: PVP2020-21792

DOI: https://doi.org/10.1115/PVP2020-21792

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Topics: Failure, Fluids, Fracture (Materials), Heat exchangers, Numerical analysis, Pressure, Shells, Stress, Stress corrosion cracking

Proceedings Papers

Ultrasonic Nondestructive Evaluation of Stress Corrosion Crack in Welded Steel Plate

Zhaoyun Ma, Lingyu Yu, Poh-Sang Lam, Robert L. Sindelar, Andrew J. Duncan, Thanh-Tam Truong, Yuh J. Chao

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A021, August 3, 2020

Paper No: PVP2020-21794

DOI: https://doi.org/10.1115/PVP2020-21794

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Topics: Imaging, Nondestructive evaluation, Radioactive wastes, Steel, Stress corrosion cracking

Proceedings Papers

Effect of High-Pressure Hydrogen and Water Impurity on Aluminum Alloys

Chris San Marchi, Martina Schwarz, Joseph Ronevich

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A089, August 3, 2020

Paper No: PVP2020-21277

DOI: https://doi.org/10.1115/PVP2020-21277

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Topics: Aluminum alloys, High pressure (Physics), Hydrogen, Water, Fracture (Process), Pressure, Stress corrosion cracking, Aluminum, Density, Fatigue

Proceedings Papers

Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds

Amanda Jenks, Warren H. Bamford

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A004, August 3, 2020

Paper No: PVP2020-21711

DOI: https://doi.org/10.1115/PVP2020-21711

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Topics: Alloys, Fracture (Materials), Stress corrosion cracking, Welded joints

Proceedings Papers

Prediction of Collapse Load Reduction due to Non-Aligned Multiple Flaws

Fuminori Iwamatsu, Katsumasa Miyazaki, Koichi Saito

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A055, August 3, 2020

Paper No: PVP2020-21806

DOI: https://doi.org/10.1115/PVP2020-21806

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Topics: Collapse, Stress, Fracture (Materials), Fracture (Process), Finite element analysis, Fitness-for-service, Ductile fracture, Flat plates, ASME Boiler and Pressure Vessel Code, Boilers

Proceedings Papers

Example Application of Code Case N-894 Rules for Weld Overlay of Thermal Fatigue Cracking

Christopher Lohse, Richard Bax, Minji Fong, Charles Fourcade, Do Jun Shim

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A100, August 3, 2020

Paper No: PVP2020-21760

DOI: https://doi.org/10.1115/PVP2020-21760

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Topics: Fatigue cracks, Overlays (Materials engineering), Fatigue, Filler metals, Maintenance, Boiling water reactors, Compression, Nickel alloys, Pressurized water reactors, Stainless steel

Proceedings Papers

Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP

Akihiro Mano, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A063, August 3, 2020

Paper No: PVP2020-21427

DOI: https://doi.org/10.1115/PVP2020-21427

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Topics: Fracture mechanics, Stress corrosion cracking, Water, Stress, Boiling water reactors, Collaboration, Failure, Fatigue, Nuclear power, Nuclear power stations

Proceedings Papers

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

Andrew J. Duncan, Poh-Sang Lam, Robert L. Sindelar

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A108, August 3, 2020

Paper No: PVP2020-21774

DOI: https://doi.org/10.1115/PVP2020-21774

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Topics: Deliquescence, Fracture (Materials), Spent nuclear fuels, Stress, Stress corrosion cracking, Welding, Electrical discharge machining, Corrosion, Stainless steel, Temperature

2 3 4 5

NARROW

Pilot Study on Seismic Fragility Evaluation for Degraded Austenitic Stainless Steel Piping Using the Probabilistic Fracture Mechanics Code PASCAL-SP

Further Development of Probabilistic Leak-Before-Break Methods

Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material

Thermal Stress Analysis of a Spent Nuclear Fuel Canister

Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR

Benchmarking Study on Probabilistic Fracture Mechanics Analysis Codes xLPR and PASCAL-SP Considering Primary Water Stress Corrosion Cracking

Technical Basis Summary for Code Case N-860: Inspection Requirements and Evaluation Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems

Stress Analysis of Tubes During Die Expansion Process

Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking

A Feasibility Study on Crack Repair in Austenitic Stainless Steel Dry Storage Canisters Using Isothermal Friction Stir Welding

Deployment of Laser Peening to Prevent CISCC of Nuclear Fuel Dry Storage Canisters

Tempering Response in Type 410 Stainless Steel Welds for Petrochemical Application

Impact of Grooves in Hydraulically Expanded Tube-to-Tubesheet Joints

Ultrasonic Nondestructive Evaluation of Stress Corrosion Crack in Welded Steel Plate

Effect of High-Pressure Hydrogen and Water Impurity on Aluminum Alloys

Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds

Prediction of Collapse Load Reduction due to Non-Aligned Multiple Flaws

Example Application of Code Case N-894 Rules for Weld Overlay of Thermal Fatigue Cracking

Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

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