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Proceedings Papers

Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products

Zhirui Jiang
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92012
https://doi.org/10.1115/ICONE29-92012
View Paper titled, Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products
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Topics: Control systems, Nuclear power, Probabilistic safety assessment, Simulation, Algorithms, Failure, Failure mechanisms, Probability, Reliability, Deformation
Proceedings Papers

Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance

Jianming Yu, Yibiao Cai
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91638
https://doi.org/10.1115/ICONE29-91638
View Paper titled, Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance
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Topics: Condition monitoring, Fault diagnosis, Maintenance, Monitoring systems, Nuclear power stations, Pattern recognition, Economics , Safety, Carbon, Construction
Proceedings Papers

Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology

Guilian Shi, Huang Xiaojin, Mo Changyu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89387
https://doi.org/10.1115/ICONE29-89387
View Paper titled, Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology
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Topics: Circuits, Failure, Physics, Electronic equipment, Hardware, Design, Failure mechanisms, Nuclear power, Nuclear power stations, Time series
Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93417
https://doi.org/10.1115/ICONE29-93417
View Paper titled, Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature
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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis
Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66591
https://doi.org/10.1115/ICONE28-66591
View Paper titled, Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64300
https://doi.org/10.1115/ICONE28-64300
View Paper titled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Evaluation of Interface Stresses and Cladding-Cladding Delamination Failures In U-Mo Fuel Plates

Hakan Ozaltun
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A018, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65840
https://doi.org/10.1115/ICONE28-65840
View Paper titled, Evaluation of Interface Stresses and Cladding-Cladding Delamination Failures In U-Mo Fuel Plates
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Topics: Cladding systems (Building), Delamination, Failure, Failure mechanisms, Fuels, Plates (structures), Stress
Proceedings Papers

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

E. E. Taapopi, H. Wang, J. Zhou
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64081
https://doi.org/10.1115/ICONE28-64081
View Paper titled, Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank
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Topics: Accidents, Boilers, Computers, Dynamic systems, Errors, Failure, Failure mechanisms, Nuclear power stations, Pressure, Probability
Proceedings Papers

Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor

Ying Yue, Walter Villanueva, Hongdi Wang, Dingqu Wang
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, V001T01A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16236
https://doi.org/10.1115/ICONE2020-16236
View Paper titled, Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor
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Topics: Accidents, Boiling water reactors, Failure, Failure mechanisms, Instrumentation, Thermomechanics
Proceedings Papers

Reliability Assessment of NPP System for Risk Management Based on an Information Reasoning Methodology

Guixia Zhu, Tianmi Zhou, Yugang Qian, Chongchong Liu, Hongxing Lu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A042, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16482
https://doi.org/10.1115/ICONE2020-16482
View Paper titled, Reliability Assessment of NPP System for Risk Management Based on an Information Reasoning Methodology
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Topics: Nuclear power stations, Reliability, Risk management, Fault diagnosis, Failure mechanisms, Modeling, Probability, Risk, Safety, System failures
Proceedings Papers

Standby Equipment Reliability Data Analysis on Risk Monitor of Nuclear Power Plant

Yingfei Ma, Zhijian Zhang, He Wang, Sijuan Chen, Anqi Xu, Gangyang Zheng
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A025, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82590
https://doi.org/10.1115/ICONE26-82590
View Paper titled, Standby Equipment Reliability Data Analysis on Risk Monitor of Nuclear Power Plant
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Topics: Nuclear power stations, Reliability, Risk monitoring, Failure, Stress, Failure mechanisms, Parameter estimation
Proceedings Papers

Finite Element Analysis for Fuel Assembly Structural Behavior

Youngik Yoo, Kyounghong Kim, Kyongbo Eom, Seongki Lee, Jongsung Yoo
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A030, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81621
https://doi.org/10.1115/ICONE26-81621
View Paper titled, Finite Element Analysis for Fuel Assembly Structural Behavior
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Topics: Finite element analysis, Fuels, Manufacturing, Accidents, Computer software, Failure mechanisms, Finite element model, Mechanical behavior, Mechanical testing, Radioactive substances
Proceedings Papers

Investigation on Breakaway Oxidation Behavior of CZ Alloys

Chang-yuan Gao, Liu-tao Chen, Lin Shi, Yang Xu, Jun Tan, Yong-jun Deng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A026, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81541
https://doi.org/10.1115/ICONE26-81541
View Paper titled, Investigation on Breakaway Oxidation Behavior of CZ Alloys
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Topics: Alloys, Oxidation, China, Hydrogen, Nuclear power, Steam, Accidents, Coolants, Failure mechanisms, Fuels
Proceedings Papers

Assessment of Failure Modes of Monolithic Fuel Plates

Hakan Ozaltun, Pavel G. Medvedev, Barry H. Rabin
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A055, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82437
https://doi.org/10.1115/ICONE26-82437
View Paper titled, Assessment of Failure Modes of Monolithic Fuel Plates
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Topics: Failure mechanisms, Fuels, Plates (structures), Failure, Irradiation (Radiation exposure), Tension, Fuel systems, Porosity, Simulation results, Thermomechanics
Proceedings Papers

Safety Analysis Model of DUCG Based on FMEA/FTA

Zhenxu Zhou, Hao Nie, Chunling Dong, Qin Zhang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A018, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81484
https://doi.org/10.1115/ICONE26-81484
View Paper titled, Safety Analysis Model of DUCG Based on FMEA/FTA
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Topics: Failure mode and effects analysis, Safety, Aerospace industry, Algorithms, Bridges (Structures), Cycles, Failure mechanisms, Modeling, Nuclear industry, Petrochemicals
Proceedings Papers

A New Safety Analysis Method of Control Rod Ejection Accident in PWR NPP Based on the Failure of Causal Relationship

Shiyu Yan, Hua Liu, Zhaohui Liu, Xiaohua Yang, Meng Li, Zhi Chen
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81879
https://doi.org/10.1115/ICONE26-81879
View Paper titled, A New Safety Analysis Method of Control Rod Ejection Accident in PWR NPP Based on the Failure of Causal Relationship
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Topics: Accidents, Failure, Nuclear power stations, Pressurized water reactors, Safety, Design, Simulation, Acceptance criteria, Computer software, Dynamics (Mechanics)
Proceedings Papers

Approach to UK SMR Component Design

Christopher D. Bell
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A003, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81188
https://doi.org/10.1115/ICONE26-81188
View Paper titled, Approach to UK SMR Component Design
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Topics: Design, Inspection, Manufacturing, Safety, Carbon, Design for Manufacturing, Energy generation, Failure, Failure mechanisms, Nuclear power stations
Proceedings Papers

Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor

Huang Yi, Zhang Tian-yi, Wang Jun, Yuan Yu-chen, Dong Xin
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81183
https://doi.org/10.1115/ICONE26-81183
View Paper titled, Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor
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Topics: Boilers, Reliability, Sodium fast reactors, Failure mechanisms, Design, Fast neutron reactors, Event history analysis, Failure, Failure mode and effects analysis, Filters
Proceedings Papers

FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty

Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82048
https://doi.org/10.1115/ICONE26-82048
View Paper titled, FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty
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Topics: Nuclear power stations, Safety, Uncertainty, Computer software, Reliability, Failure mechanisms, Testing, Aerospace industry, Errors, Failure data
Proceedings Papers

NPP I&C Safety Assessment by Aggregation of Formal Techniques

Eugene Babeshko, Vyacheslav Kharchenko, Kostiantyn Leontiiev, Oleg Odarushchenko, Oleksiy Strjuk
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82270
https://doi.org/10.1115/ICONE26-82270
View Paper titled, NPP I&C Safety Assessment by Aggregation of Formal Techniques
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Topics: Nuclear power stations, Safety, Computer software, Failure mode and effects analysis, Computers, Control systems, Design, Failure mechanisms, Flow (Dynamics), Hardware