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Proceedings Papers

Common Cause Failure Analysis and Countermeasure of Digital Instrument and Control System in Nuclear Power Plant

Ping Wang, Lisheng Hu
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92984
https://doi.org/10.1115/ICONE29-92984
View Paper titled, Common Cause Failure Analysis and Countermeasure of Digital Instrument and Control System in Nuclear Power Plant
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Topics: Control systems, Countermeasures, Defense industry, Failure analysis, Instrumentation, Nuclear power stations, Safety
Proceedings Papers

The Research on Common Cause Failure Analysis and Countermeasures for Nuclear Safety Ventilation and Air Conditioning System

Yongsen Peng, Zhengjie Liu
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A062, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93557
https://doi.org/10.1115/ICONE29-93557
View Paper titled, The Research on Common Cause Failure Analysis and Countermeasures for Nuclear Safety Ventilation and Air Conditioning System
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Topics: Air conditioning, Countermeasures, Failure, Failure analysis, Safety, Ventilation, Nuclear power stations, Hazard analysis, Regulations, Risk
Proceedings Papers

Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases

Eishiro Higo, Shota Soga, Hiromichi Miura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A010, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16819
https://doi.org/10.1115/ICONE2020-16819
View Paper titled, Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases
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Topics: Failure, Failure analysis, Databases, Probability, Nuclear power stations, Performance, Probabilistic risk assessment
Proceedings Papers

Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method

Jinya Katsuyama, Yoshihito Yamaguchi, Yinsheng Li
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A032, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82568
https://doi.org/10.1115/ICONE26-82568
View Paper titled, Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method
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Topics: Creep, Damage, Evaluation methods, Pipes, Accidents, Constitutive equations, Failure, Failure analysis, Finite element analysis, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Stress Corrosion Cracking Behavior in Liquid/Vapors of Boiling Magnesium Chloride Solution of 304L/316L/690 for Heavy-Water Collection Tubing in CANDU Nuclear Power Plant

Guangfu Li, Liang Zhao, Xinghong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A095, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67314
https://doi.org/10.1115/ICONE25-67314
View Paper titled, Stress Corrosion Cracking Behavior in Liquid/Vapors of Boiling Magnesium Chloride Solution of 304L/316L/690 for Heavy-Water Collection Tubing in CANDU Nuclear Power Plant
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Topics: Boiling, Magnesium (Metal), Nuclear power stations, Stress corrosion cracking, Tubing, Vapors, Water, Cracking (Materials), Fracture (Process), Alloys
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66591
https://doi.org/10.1115/ICONE25-66591
View Paper titled, Research on the Structure Integrity Analysis of Flywheel of Reactor Coolant Pump in Nuclear Power Plant
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Topics: Flywheels, Nuclear power stations, Nuclear reactor coolants, Pumps, Failure, Stress, Damage, Design, Failure analysis, Kinetic energy
Proceedings Papers

Innovative Methodology of Ranking Cooling Towers Based on Structural Safety Margin

Nhu-Cuong Tran, Charles Toulemonde, François Beaudouin, Christian Meuwisse, Nicolas Schmitt, Abderrazzaq El-Yazidi, Alexis Courtois, Yves Genest, Sylvain Moriceau
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A042, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67596
https://doi.org/10.1115/ICONE25-67596
View Paper titled, Innovative Methodology of Ranking Cooling Towers Based on Structural Safety Margin
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Topics: Cooling towers, Safety, Risk, Shells, Columns (Structural), Failure, Maintenance, Corrosion, Damage, Deformation
Proceedings Papers

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

Zhou Lifeng, Cheng Zhaoyu, Cai Jiafan, Tang Yi
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A028, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66999
https://doi.org/10.1115/ICONE25-66999
View Paper titled, In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR
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Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water
Proceedings Papers

Failure Analysis of the Branch Connection Leakage on Primary Pipeline of the Primary Heat Transport System and the Maintenance Strategy Investigation for the Similar Connections

Liang Zhao, Ting Zhao, Fengmin Chu, Jianqun Hu, Xin Wang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A032, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16235
https://doi.org/10.1115/ICONE21-16235
View Paper titled, Failure Analysis of the Branch Connection Leakage on Primary Pipeline of the Primary Heat Transport System and the Maintenance Strategy Investigation for the Similar Connections
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Topics: Failure analysis, Heat, Leakage, Maintenance, Pipelines, Failure, Metals, Stainless steel, Stress corrosion cracking, Testing
Proceedings Papers

The Failure Analysis and Processing of Digital Reactor Protection System

Jun Zhao, Xing Zhou, Jin Hu, Yanling Yu
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T13A008, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15423
https://doi.org/10.1115/ICONE21-15423
View Paper titled, The Failure Analysis and Processing of Digital Reactor Protection System
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Topics: Failure analysis, Reactor protection systems, Failure, Nuclear power stations, Reliability, China, Maintenance, Pressurized water reactors, Risk, Security
Proceedings Papers

Failure Analysis and Strategy Investigation of the Rupture on the Gland Seal Steam Drain Pipeline of the Reheat Stop Valve

Liang Zhao, Guangfu Li, Jianqun Hu, Weidong Zhao, Mingjun Chen
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A025, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15916
https://doi.org/10.1115/ICONE21-15916
View Paper titled, Failure Analysis and Strategy Investigation of the Rupture on the Gland Seal Steam Drain Pipeline of the Reheat Stop Valve
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Topics: Failure analysis, Pipelines, Rupture, Steam, Valves, Pipes, Corrosion, Wall thickness, Failure, Fracture (Materials)
Proceedings Papers

Failure Analysis and Strategy Investigation on Local Thinning of the Warm-Up Line in Auxiliary Feed Water Pump System

Liang Zhao, Kunjie Luo, Jianqun Hu, Xin Wang, Mingjun Chen
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A037, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16330
https://doi.org/10.1115/ICONE21-16330
View Paper titled, Failure Analysis and Strategy Investigation on Local Thinning of the Warm-Up Line in Auxiliary Feed Water Pump System
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Topics: Failure analysis, Feedwater, Pumps, Corrosion, Finite element methods, Finite element model, Flow (Dynamics), Inspection, Maintenance, Nuclear power stations
Proceedings Papers

An Addendum: Probabilistic Failure Analysis of a Residual Heat Removal Heat Exchanger During Postulated Loss of Coolant Accident

Matt Solom, Christopher Pannier, Christopher Chance, Robert Seager, Alan Lee, Jordan Green, Tam Duong, Paola Alicea
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 343-347, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54636
https://doi.org/10.1115/ICONE20-POWER2012-54636
View Paper titled, An Addendum: Probabilistic Failure Analysis of a Residual Heat Removal Heat Exchanger During Postulated Loss of Coolant Accident
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Topics: Accidents, Coolants, Failure analysis, Heat, Heat exchangers, Failure, Probability, Simulation, Flow (Dynamics), FORTRAN
Proceedings Papers

Life Cycle Management of Gas Turbine: An OEM Independent Approach

Joop Kraijesteijn, Eric Vogelaar
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, 499-506, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55020
https://doi.org/10.1115/ICONE20-POWER2012-55020
View Paper titled, Life Cycle Management of Gas Turbine: An OEM Independent Approach
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Topics: Gas turbines, Life cycle management, Inspection, Failure analysis, Maintenance, Quality control, Combustion, Compressors, Dynamics (Mechanics), Nondestructive evaluation
Proceedings Papers

Teaching of Nuclear Power Plant Safety at the National Technical University of Ukraine Within the New Course in Safety Culture

Vasilij V. Begun, Sergij V. Begun, Olena O. Kilina
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 423-429, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54814
https://doi.org/10.1115/ICONE20-POWER2012-54814
View Paper titled, Teaching of Nuclear Power Plant Safety at the National Technical University of Ukraine Within the New Course in Safety Culture
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Topics: Nuclear power stations, Safety, Teaching, Education, Nuclear industry, Students, Nuclear power, Probabilistic safety assessment, Accidents, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986
Proceedings Papers

Thermal Loading Failure Analysis of Molten Pool in the Reactor Vessel

Xiao Yang, Yanhua Yang, Bo Kuang, Xiaoliang Fu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 577-581, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29819
https://doi.org/10.1115/ICONE18-29819
View Paper titled, Thermal Loading Failure Analysis of Molten Pool in the Reactor Vessel
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Topics: Failure analysis, Reactor vessels, Accidents, Critical heat flux, Uncertainty, Cooling, Damage, Hazards, Heat flux, Heat transfer
Proceedings Papers

Insights From Plant Specific Common Cause Failure Analysis

Young G. Jo
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 83-88, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49232
https://doi.org/10.1115/ICONE12-49232
View Paper titled, Insights From Plant Specific Common Cause Failure Analysis
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Topics: Computer software, Databases, Failure, Failure analysis, Internet
Proceedings Papers

Practical Procedures for Estimation of Plant Specific Common Cause Failure Quantification Parameters for Plants With Accumulated Operating Experiences

Young G. Jo
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 65-75, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49215
https://doi.org/10.1115/ICONE12-49215
View Paper titled, Practical Procedures for Estimation of Plant Specific Common Cause Failure Quantification Parameters for Plants With Accumulated Operating Experiences
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Topics: Failure, Failure analysis
Proceedings Papers

The Human Bathtub: Safety and Risk Predictions Including the Dynamic Probability of Operator Errors

Romney B. Duffey, John W. Saull
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 243-248, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89476
https://doi.org/10.1115/ICONE14-89476
View Paper titled, The Human Bathtub: Safety and Risk Predictions Including the Dynamic Probability of Operator Errors
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Topics: Errors, Probability, Risk, Safety, Failure, Performance, Accidents, Fittings, Reliability, Transients (Dynamics)