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Proceedings Papers

Crack Propagation Analysis of Dissimilar Metal Weld for Steam Generator Nozzle Safety End

Shuang Qi, Wenxin Xiang, Ping Huang, Fangmao Ning, Minyu Fan, Lei Qi, Mingya Chen, Jun Xu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A074, August 8–12, 2022
Paper No: ICONE29-93289
DOI: https://doi.org/10.1115/ICONE29-93289
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Topics: Boilers, Crack propagation, Metals, Nozzles, Safety
Proceedings Papers

IHSI Effectiveness for Crack Propagation Observed at Hamaoka PLR Piping

Hideki Yuya, Kouji Yamada, Takao Sasayama
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A004, August 4–5, 2020
Paper No: ICONE2020-16090
DOI: https://doi.org/10.1115/ICONE2020-16090
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Topics: Crack propagation, Electromagnetic induction, Fracture (Materials), Heat, Pipes, Stress, Ultrasonic testing, Cutting, Plant construction
Proceedings Papers

Research on the Structure Integrity Analysis of Flywheel of Reactor Coolant Pump in Nuclear Power Plant

Jian Zhang, Yongde Zuo, Xingjiang Chen, Qinghong Zhang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A055, July 2–6, 2017
Paper No: ICONE25-66591
DOI: https://doi.org/10.1115/ICONE25-66591
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Topics: Flywheels, Nuclear power stations, Nuclear reactor coolants, Pumps, Failure, Stress, Damage, Design, Failure analysis, Kinetic energy
Proceedings Papers

Biaxial-EDC Test Attempts With Pre-Cracked Zircaloy-4 Cladding Tubes

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A034, July 2–6, 2017
Paper No: ICONE25-67602
DOI: https://doi.org/10.1115/ICONE25-67602
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Topics: Cladding systems (Building), Failure, Fracture (Materials), Fuels, Stress, Accidents, Bonding, Compression, Crack propagation, Deformation
Proceedings Papers

HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures

John Sulley, David Stewart
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A034, June 26–30, 2016
Paper No: ICONE24-61106
DOI: https://doi.org/10.1115/ICONE24-61106
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Topics: Foundry coatings, Quality control, Hardening, Wear, Erosion, Stress, Cobalt, Contamination, Corrosion resistance, Crack propagation
Proceedings Papers

Fracture Resistance of Cast Austenitic Stainless Steels

Y. Chen, W-Y. Chen, A. S. Rao, Z. Li, Y. Yang, B. Alexandreanu, K. Natesan
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A022, June 26–30, 2016
Paper No: ICONE24-60736
DOI: https://doi.org/10.1115/ICONE24-60736
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Topics: Fracture (Materials), Stainless steel, Neutrons, Irradiation (Radiation exposure), Ferrites (Magnetic materials), Fracture toughness, Alloys, Embrittlement, Light water reactors, Corrosion resistance
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR

Shigeru Takaya, Hideo Machida, Yoshio Kamishima
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A005, July 7–11, 2014
Paper No: ICONE22-30570
DOI: https://doi.org/10.1115/ICONE22-30570
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Topics: Japan Society of Mechanical Engineers, Reliability, Failure, Breeder reactors, Crack propagation, Creep, Damage, Fatigue, Modeling, Probability
Proceedings Papers

Field Experience of Water Jet Peening Application on BWR Reactor Internals With Cracked Surfaces

Ren Morinaka, Kunihiro Hasegawa, Masashi Fukaya, Yuji Matsui, Hisamitsu Hatoh, Noboru Saito, Fujio Yoshikubo, Akihiro Kanno
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 241-250, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55070
DOI: https://doi.org/10.1115/ICONE20-POWER2012-55070
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Topics: Boiling water reactors, Shot peening, Water, Fracture (Materials), Nuclear power, Crack propagation, JSME Standards, Nuclear power stations, Nuclear reactors, Stress corrosion cracking
Proceedings Papers

Stress Corrosion Cracking Behavior Around Interface Between Nickel Base Alloy (Alloy182) and Low-Alloy Steel

Yu Itabashi, Yohei Sakakibara, Masahiro Takanashi, Guen Nakayama, Takashi Hirano
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 573-582, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55266
DOI: https://doi.org/10.1115/ICONE20-POWER2012-55266
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Topics: Alloys, Nickel, Steel, Stress corrosion cracking, Fracture (Materials), Stress, Water, Electrical conductivity, Light water reactors, Coolants
Proceedings Papers

Multiphysics Modeling and Simulation for Stress Corrosion Cracking Considering Oxygen Atom Diffusion Along Grain Boundary

Takahiro Igarashi, Yoshiteru Aoyagi, Yoshiyuki Kaji
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 129-133, May 17–21, 2010
Paper No: ICONE18-29337
DOI: https://doi.org/10.1115/ICONE18-29337
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Topics: Atoms, Diffusion (Physics), Grain boundaries, Modeling, Oxygen, Simulation, Stress corrosion cracking, Fracture (Materials), Crack propagation, Stress
Proceedings Papers

Effects of Laser Peening Treatment on High Cycle Fatigue and Crack Propagation Behaviors in Austenitic Stainless Steel

Yasuo Ochi, Kiyotaka Masaki, Takashi Matsumura, Takaaki Ikarashi, Yuji Sano
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 701-707, July 12–16, 2009
Paper No: ICONE17-75821
DOI: https://doi.org/10.1115/ICONE17-75821
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Topics: Crack propagation, High cycle fatigue, Laser hardening, Stainless steel, Stress, Fatigue cracks, Fatigue strength, Fracture (Materials), Irradiation (Radiation exposure), Lasers
Proceedings Papers

Development of Alternative Reductant Application in PWR Primary Systems

Masafumi Domae, Hirotaka Kawamura, Taku Ohira
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 575-582, July 12–16, 2009
Paper No: ICONE17-75551
DOI: https://doi.org/10.1115/ICONE17-75551
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Topics: Pressurized water reactors, Hydrogen, Methanol, Coolants, Stainless steel, Water, Corrosion, Crack propagation, Electrolytic corrosion, Public utilities
Proceedings Papers

Development of Advanced System for Early Detection of Primary Coolant Circuit Piping Leaks

Petros Hovhannisyan
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 815-820, July 12–16, 2009
Paper No: ICONE17-75810
DOI: https://doi.org/10.1115/ICONE17-75810
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Topics: Circuits, Coolants, Leakage, Pipes, Fracture (Materials), Pipelines, Deformation, Maintenance, Nuclear power stations, Safety
Proceedings Papers

PWSCC of Nickel Base Alloys in Vapor Phase Environment of Pressurizer

Takao Tsuruta, Kenji Sato, Seiji Asada, Takaaki Kobayashi, Koji Okimura, Nariyasu Matsubara
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 571-573, May 11–15, 2008
Paper No: ICONE16-48377
DOI: https://doi.org/10.1115/ICONE16-48377
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Topics: Alloys, Nickel, Vapors, Liquid films, Water, Chemistry, Metals, Crack propagation, Fracture (Materials), Pressurized water reactors
Proceedings Papers

Steam Generator In-Service Inspections at Paks NPP

Miklo´s Do´czi
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 1-5, May 11–15, 2008
Paper No: ICONE16-48063
DOI: https://doi.org/10.1115/ICONE16-48063
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Topics: Boilers, In-service inspection, Nuclear power stations, Eddies (Fluid dynamics), Eddy currents (Electricity), Inspection, Condensers (steam plant), Corrosion, Damage, Eddy current testing
Proceedings Papers

Validation of a Computer Code for Analysis of Elasto-Plastic Crack Propagation

Afzaal M. Malik, Jawad Khawar
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 77-87, May 11–15, 2008
Paper No: ICONE16-48274
DOI: https://doi.org/10.1115/ICONE16-48274
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Topics: Computers, Crack propagation, Finite element methods, Fracture (Materials), Stress, Aerospace industry, Brittleness, Service life (Equipment), Structural failures