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Proceedings Papers

Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants

Bai Lin, Liang Xiaoru
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92165
https://doi.org/10.1115/ICONE29-92165
View Paper titled, Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants
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Topics: Carbon steel, Nuclear power stations, Pressurized water reactors, Welding
Proceedings Papers

Heating Impact on Corrosion Mechanism of Carbon Steel Surrounded by Bentonite

Masao Uyama, Hiroyuki Saito, Tomoya Iioka
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A056, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16765
https://doi.org/10.1115/ICONE2020-16765
View Paper titled, Heating Impact on Corrosion Mechanism of Carbon Steel Surrounded by Bentonite
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Topics: Carbon steel, Corrosion, Electrochemical impedance spectroscopy, Heating, Radioactive wastes, Steel
Proceedings Papers

Preliminary Research on the Oxidation Effect of the Carbon Steel Plate of Downward Facing Pool Boiling by Two-Dimensional Image

Kai Wang, Nejdet Erkan, Koji Okamoto
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A067, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82019
https://doi.org/10.1115/ICONE26-82019
View Paper titled, Preliminary Research on the Oxidation Effect of the Carbon Steel Plate of Downward Facing Pool Boiling by Two-Dimensional Image
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Topics: Carbon steel, Oxidation, Pool boiling, Critical heat flux, Heart failure, Copper, Cooling, Heating, Reactor vessels, Bubbles
Proceedings Papers

Welded Joint Evaluation for Chromium Controlled Carbon Steel Piping to Improve FAC Resistance

Yoshio Uemoto, Takahiro Kawabe, Hiroyuki Shibata, Shoh Tarasawa, Hiroshi Asano, Junya Kaneda
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A022, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81913
https://doi.org/10.1115/ICONE26-81913
View Paper titled, Welded Joint Evaluation for Chromium Controlled Carbon Steel Piping to Improve FAC Resistance
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Topics: Carbon steel, Pipes, Welded joints, Welding, Alloy steel, Alloys, Condensed matter, Construction, Corrosion, Feedwater
Proceedings Papers

Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping

Zhenshun Liu, Hongdong Zhen
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81640
https://doi.org/10.1115/ICONE26-81640
View Paper titled, Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping
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Topics: Carbon steel, Fatigue cracks, Pipes, Transients (Dynamics), Fracture (Materials), Stress, ASME Standards, Fatigue
Proceedings Papers

Computation of Solid Melting With Wall Boiling Under External Reactor Vessel Cooling

Hyuk-Jin Song, Jong Woon Park
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81499
https://doi.org/10.1115/ICONE26-81499
View Paper titled, Computation of Solid Melting With Wall Boiling Under External Reactor Vessel Cooling
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Topics: Boiling, Computation, Cooling, Melting, Reactor vessels, Flow (Dynamics), Water, Physics, Carbon steel, Convection
Proceedings Papers

Corrosion Susceptibility in High Temperature Liquid/Vapor Environments of Materials for Tubing of Heavy-Water Collection System in CANDU Nuclear Power Plant

Guangfu Li, Liang Zhao, Xinghong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A086, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67218
https://doi.org/10.1115/ICONE25-67218
View Paper titled, Corrosion Susceptibility in High Temperature Liquid/Vapor Environments of Materials for Tubing of Heavy-Water Collection System in CANDU Nuclear Power Plant
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Topics: Corrosion, High temperature, Nuclear power stations, Tubing, Vapors, Water, Stainless steel, Temperature, Alloys, Carbon steel
Proceedings Papers

Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN

Goro Soejima, Hiroki Iwai, Yasuyuki Nakamura, Hirokazu Hayashi, Haruhiko Kadowaki, Hiroyuki Mizui, Kazuya Sano
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A019, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66950
https://doi.org/10.1115/ICONE25-66950
View Paper titled, Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN
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Topics: Contamination, Technology development, Laser cutting, Cutting, Nuclear decommissioning, Water, Pipes, Zirconium alloys, Aluminum, Boiling
Proceedings Papers

The Current Status of CANDU Steam Generators

Matthew Naraine, Jovica Riznic
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A001, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66001
https://doi.org/10.1115/ICONE25-66001
View Paper titled, The Current Status of CANDU Steam Generators
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Topics: Boilers, Chemistry, Design, Pressurized water reactors, Tubing, Carbon steel, Collaboration, Databases, Failure mechanisms, Industrial research
Proceedings Papers

Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression

Chunzhen Yang, Jingquan Liu, Yuyun Zeng, Muhammad Saeed
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, V001T01A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61114
https://doi.org/10.1115/ICONE24-61114
View Paper titled, Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression
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Topics: Support vector machines, Uncertainty, Modeling, Nuclear power stations, Algorithms, Carbon steel, In-service inspection, Maintenance, Pipes, Sampling methods
Proceedings Papers

AP1000 ® Submergence Testing of Service Level I Protective Coatings

Matthew R. Beenken, Christina L. Rocco, Timothy S. Andreychek
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, V001T03A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60228
https://doi.org/10.1115/ICONE24-60228
View Paper titled, AP1000 ® Submergence Testing of Service Level I Protective Coatings
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Topics: Protective coatings, Testing, Coatings, Containment, Temperature, Accidents, Coolants, Design, Fluids, Pressure
Proceedings Papers

Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies

Sunil Nijhawan
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60689
https://doi.org/10.1115/ICONE24-60689
View Paper titled, Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies
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Topics: Accidents, Design, Boilers, Pressure, Containment, Heat, Safety, Accident management, Analytical methods, Leakage
Proceedings Papers

Improvement of FAC Maintenance Program Issued From BRT-CICERO™ via CFD Calculations

Elodie Gipon
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A003, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60136
https://doi.org/10.1115/ICONE24-60136
View Paper titled, Improvement of FAC Maintenance Program Issued From BRT-CICERO™ via CFD Calculations
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Topics: Computational fluid dynamics, Maintenance, Pipes, Computer software, Flow (Dynamics), Nuclear power stations, Algorithms, Corrosion, Feedback, Mass transfer
Proceedings Papers

Proposal for Evaluation With Strain-Based Criterion of Impact Phenomena Between Steel Structure and Tornado Missile

Yuko Sakamoto, Koji Shirai, Toshiko Udagawa, Shunsuke Kondo
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, V001T03A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60171
https://doi.org/10.1115/ICONE24-60171
View Paper titled, Proposal for Evaluation With Strain-Based Criterion of Impact Phenomena Between Steel Structure and Tornado Missile
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Topics: Missiles, Steel, Japan Society of Mechanical Engineers, Pressurized water reactors, Accidents, Carbon steel, Containment, Deformation, Fracture (Materials), Fracture (Process)
Proceedings Papers

3D Linear Bifurcation Analysis of Steel Containment Vessel

Jay Schmidt, Bernd Laskewitz
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, V001T03A018, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60673
https://doi.org/10.1115/ICONE24-60673
View Paper titled, 3D Linear Bifurcation Analysis of Steel Containment Vessel
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Topics: Bifurcation, Containment vessels, Steel, Shells, Stability, Buckling, Containment, Stress, ASME Boiler and Pressure Vessel Code, ASME Standards
Proceedings Papers

Severe Accident Related Vulnerabilities, Potential Design Enhancements and Opportunities for International Cooperation in Risk Reduction in Pressurized Heavy Water Reactors

Sunil Nijhawan
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T02A002, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49574
https://doi.org/10.1115/NUCLRF2015-49574
View Paper titled, Severe Accident Related Vulnerabilities, Potential Design Enhancements and Opportunities for International Cooperation in Risk Reduction in Pressurized Heavy Water Reactors
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Topics: Accidents, Design, Heavy water reactors, Risk reduction, Fuels, Containment, Hydrogen, Nuclear fission, Pressure, Alternating current (Electricity)
Proceedings Papers

A Statistical Model for Accessing Wall Thinning Rate due to Flow Accelerated Corrosion Based on Inspection Data in Nuclear Power Plants

Yuyun Zeng, Jingquan Liu, Weilin Huang
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, V001T01A001, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30043
https://doi.org/10.1115/ICONE22-30043
View Paper titled, A Statistical Model for Accessing Wall Thinning Rate due to Flow Accelerated Corrosion Based on Inspection Data in Nuclear Power Plants
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Topics: Corrosion, Flow (Dynamics), Inspection, Nuclear power stations, Pipes, Pressurized water reactors, Alloys, Carbon steel, Circuits, Decision making
Proceedings Papers

Effects of Aging on the Thermal Conductivity of the AP1000® Containment Vessel Inorganic Zinc Coating

Thomas A. Kindred, Richard F. Wright
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, V001T03A028, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31157
https://doi.org/10.1115/ICONE22-31157
View Paper titled, Effects of Aging on the Thermal Conductivity of the AP1000® Containment Vessel Inorganic Zinc Coating
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Topics: Containment vessels, Thermal conductivity, Zinc coatings, Containment, Shells, Coating processes, Coatings, Corrosion, Cooling, Design
Proceedings Papers

The Role of CHECWORKS™ in an Effective FAC Program

David Smith, Jeffrey Horowitz
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, V001T01A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30854
https://doi.org/10.1115/ICONE22-30854
View Paper titled, The Role of CHECWORKS™ in an Effective FAC Program
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Topics: Accidents, Carbon steel, Computer software, Condensed matter, Corrosion, Engineers, Failure, Flow (Dynamics), Fossil fuels, Inspection
Proceedings Papers

Prediction Model for Oxidation Layer Thickness in Flow Accelerated Corrosion

Ruixuan Han, Yi Peng, Huailin Li
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, V001T01A009, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30489
https://doi.org/10.1115/ICONE22-30489
View Paper titled, Prediction Model for Oxidation Layer Thickness in Flow Accelerated Corrosion
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Topics: Corrosion, Flow (Dynamics), Oxidation, Temperature, Carbon steel