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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

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

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

Investigation of Chloride-Induced Stress Corrosion Cracking for AISI 304/304L Stainless Steel Using Notched Bar Specimens

Jae-Yoon Jeong, Yun-Jae Kim, Poh-Sang Lam, Andrew Duncan, Myeong-Woo Lee
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A106, August 3, 2020
Paper No: PVP2020-21399
DOI: https://doi.org/10.1115/PVP2020-21399
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Topics: Corrosion, Spent nuclear fuels, Stainless steel, Stress corrosion cracking
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
Proceedings Papers

A52M/SA52 Dissimilar Metal RPV Repair Weld: Experimental Evaluation and Post-Weld Characterizations

Iikka Virkkunen, Mikko Peltonen, Henrik Sirén, Pekka Nevasmaa, Caitlin Huotilainen, Heikki Keinänen, Juha Kuutti, Aloshious Lambai, Gaurav Mohanty, Mari Honkanen
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A110, August 3, 2020
Paper No: PVP2020-21236
DOI: https://doi.org/10.1115/PVP2020-21236
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Topics: Maintenance, Metals, Welding, Cracking (Materials), Fracture (Process), Reactor vessels, Alloys, Fracture (Materials), Heat, Alloy steel
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

Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment

Y. Chen, B. Alexandreanu, A. S. Rao
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A071, August 3, 2020
Paper No: PVP2020-21141
DOI: https://doi.org/10.1115/PVP2020-21141
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Topics: Embrittlement, Fracture (Materials), Fracture (Process), Fracture toughness, Irradiation (Radiation exposure), Light water reactors, Stress corrosion cracking
Proceedings Papers

SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA

Takuya Ogawa, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A080, August 3, 2020
Paper No: PVP2020-21670
DOI: https://doi.org/10.1115/PVP2020-21670
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Topics: Finite element analysis, Surface cracks, Welded joints, Fracture (Materials), Fracture (Process), Shapes, Fitness-for-service, Metals, Stainless steel, Base metals
Proceedings Papers

Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition

Masato Koshiishi, Hitoshi Seto, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A073, August 3, 2020
Paper No: PVP2020-21332
DOI: https://doi.org/10.1115/PVP2020-21332
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Topics: Boiling water reactors, Irradiation (Radiation exposure), Neutrons, Stainless steel, Stress corrosion cracking, Fracture (Materials), Grain boundaries, Mechanical properties
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