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Proceedings Papers

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Yuchao Wang, Daogang Lu, Fei Zhao, Yu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A071, August 8–12, 2022
Paper No: ICONE29-92039
DOI: https://doi.org/10.1115/ICONE29-92039
View Paper titled, Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants
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Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels
Proceedings Papers

The BDB-NS Hydrodynamic Model for Porous Spent Fuel Storage Racks Solved by Fourier Spectral Method

Yu Liu, Yuxuan Zhu, Fei Zhao, Dong Liu, Daogang Lu
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A023, August 8–12, 2022
Paper No: ICONE29-91760
DOI: https://doi.org/10.1115/ICONE29-91760
View Paper titled, The BDB-NS Hydrodynamic Model for Porous Spent Fuel Storage Racks Solved by Fourier Spectral Method
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Topics: Earthquakes, Spent fuel storage
Proceedings Papers

General Safety Assessment of Seismically Induced Hazards for NPPs

Guanghua Yang, Cuilian Yang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A054, August 8–12, 2022
Paper No: ICONE29-93121
DOI: https://doi.org/10.1115/ICONE29-93121
View Paper titled, General Safety Assessment of Seismically Induced Hazards for NPPs
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Topics: Earthquakes, Hazards, Nuclear power stations, Safety
Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022
Paper No: ICONE29-90172
DOI: https://doi.org/10.1115/ICONE29-90172
View Paper titled, On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads
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Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation
Proceedings Papers

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Saifeng Wu, Wenguang Liu, Wenfu He
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A045, August 8–12, 2022
Paper No: ICONE29-92541
DOI: https://doi.org/10.1115/ICONE29-92541
View Paper titled, Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators
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Topics: Friction, Mechanical properties, Bearings, Damage, Deformation, Design, Earthquakes, Errors, Rubber, Stiffness
Proceedings Papers

Seismic Behavior Study of a new Isolated Structure System With Damping Supporter for Nuclear Power Plants in a Cave or Underground

Yixin Feng, Hao Xu, Wenguang Liu, Qiang Zhang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A046, August 8–12, 2022
Paper No: ICONE29-92634
DOI: https://doi.org/10.1115/ICONE29-92634
View Paper titled, Seismic Behavior Study of a new Isolated Structure System With Damping Supporter for Nuclear Power Plants in a Cave or Underground
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Topics: Caves, Damping, Earthquakes, Nuclear power stations
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
Paper No: ICONE29-92012
DOI: 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

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Masashi Sekine, Junichi Kaneko, Takeshi Takeda
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021
Paper No: ICONE28-64117
DOI: https://doi.org/10.1115/ICONE28-64117
View Paper titled, RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions
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Topics: Accidents, Boilers, Pressurized water reactors, Rupture, Damage, Cooling, Earthquakes, Emergency core cooling systems, Failure, Feedwater
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
Paper No: ICONE28-64300
DOI: 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

Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records

Kouki Yamakawa, Masaaki Saruta, Hiroshi Moritani, Hiroaki Yamazaki, Akemi Nishida, Manabu Kawata, Kazuhiko Iigaki
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, V001T02A010, August 4–6, 2021
Paper No: ICONE28-64337
DOI: https://doi.org/10.1115/ICONE28-64337
View Paper titled, Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records
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Topics: Nuclear power stations, Vibration, Displacement, Earthquakes, Excitation, Finite element model, Deformation, Pacific Ocean, Shorelines
Proceedings Papers

Research on Earthquake Acceleration Alarm of Nuclear Power Plant

Li Liang, Pan Rong, Ren Guopeng, Zhu Xiuyun
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, V001T02A022, August 4–6, 2021
Paper No: ICONE28-64554
DOI: https://doi.org/10.1115/ICONE28-64554
View Paper titled, Research on Earthquake Acceleration Alarm of Nuclear Power Plant
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Topics: Earthquakes, Instrumentation, Nuclear power stations
Proceedings Papers

Estimation of the Amount of I-129 in the Environment Generated Due to the Decay of Te-129m Discharged by the Fukushima NPS Accident

Haruo Sato
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, V003T11A013, August 4–6, 2021
Paper No: ICONE28-65725
DOI: https://doi.org/10.1115/ICONE28-65725
View Paper titled, Estimation of the Amount of I-129 in the Environment Generated Due to the Decay of Te-129m Discharged by the Fukushima NPS Accident
Click here to open pdf in another window PDF for Estimation of the Amount of I-129 in the Environment Generated Due to the Decay of Te-129m Discharged by the Fukushima NPS Accident
Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Soil, Half-life, Radioisotopes, Earthquakes, Equilibrium (Physics), Nuclear power stations, Nuclides, Radiation (Physics)
Proceedings Papers

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Hui Fu, Daogang Lu, Yu Liu
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, V003T12A012, August 4–6, 2021
Paper No: ICONE28-64082
DOI: https://doi.org/10.1115/ICONE28-64082
View Paper titled, Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor
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Topics: Alloys, Safety, Earthquakes, Collisions (Physics), Computer simulation, Coolants, Finite element methods, Leakage, Neutrons, Nuclear fuels
Proceedings Papers

A Beyond Design Basis Earthquake Study of Operating Nuclear Fuel Cycle Facilities

Li Liang, Pan Rong, Zhu Xiuyun, Ren Guopeng
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, V003T12A026, August 4–6, 2021
Paper No: ICONE28-64514
DOI: https://doi.org/10.1115/ICONE28-64514
View Paper titled, A Beyond Design Basis Earthquake Study of Operating Nuclear Fuel Cycle Facilities
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Topics: Design, Earthquakes, Nuclear fuel cycle, Safety
Proceedings Papers

Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation

Oleksii Ishchenko, Vladislav Filonov, Yaroslav Dubyk
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A085, August 4–6, 2021
Paper No: ICONE28-65756
DOI: https://doi.org/10.1115/ICONE28-65756
View Paper titled, Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation
Click here to open pdf in another window PDF for Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation
Topics: Accidents, Cavitation, Computational fluid dynamics, Coolants, Design, Dynamic analysis, Dynamic models, Dynamic response, Dynamic stability, Dynamics (Mechanics)
Proceedings Papers

Development of Ultrasonic Measurement System for Shape and 2D Velocity Field Using Ultrasonic Velocity Profiler and Total Focusing Methods

Zeliang Zhang, Tianrun Liu, Munkhbat Batsaikhan, Hideharu Takahashi, Hiroshige Kikura
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A049, August 4–6, 2021
Paper No: ICONE28-64510
DOI: https://doi.org/10.1115/ICONE28-64510
View Paper titled, Development of Ultrasonic Measurement System for Shape and 2D Velocity Field Using Ultrasonic Velocity Profiler and Total Focusing Methods
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Topics: Fuels, Fukushima nuclear disaster, Japan, 2011, Nuclear decommissioning, Nuclear power stations, Shapes, Transducers, Ultrasonic measurement, Accidents, Radiation (Physics), Water leakage
Proceedings Papers

Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads

Masato Murohara, Akira Yamazaki, Takuya Sato, Naoto Kasahara
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A072, August 4–6, 2021
Paper No: ICONE28-65553
DOI: https://doi.org/10.1115/ICONE28-65553
View Paper titled, Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads
Click here to open pdf in another window PDF for Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads
Topics: Buckling, Reactor vessels, Failure, Design, Accidents, Deformation, Earthquakes, Fukushima nuclear disaster, Japan, 2011, High temperature, Nuclear reactor accidents
Proceedings Papers

Study on Seismic Isolation and Hi-Frequency Vibration Isolation Technology for Equipment in Nuclear Power Plant Using Aero Floating Technique

Kiyotaka Takito, Osamu Furuya, Hiroshi Kurabayashi, Kunio Sanpei
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A053, August 4–5, 2020
Paper No: ICONE2020-16940
DOI: https://doi.org/10.1115/ICONE2020-16940
View Paper titled, Study on Seismic Isolation and Hi-Frequency Vibration Isolation Technology for Equipment in Nuclear Power Plant Using Aero Floating Technique
Click here to open pdf in another window PDF for Study on Seismic Isolation and Hi-Frequency Vibration Isolation Technology for Equipment in Nuclear Power Plant Using Aero Floating Technique
Topics: Earthquakes, Nuclear power stations, Vibration isolation, Vibration, Collisions (Physics), Countermeasures, Insulation, Levitation, Pressure
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Paper No: ICONE2020-16897
DOI: https://doi.org/10.1115/ICONE2020-16897
View Paper titled, Probability of Rupture for WWER-1000 Main Piping
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

Study on the Interaction Between Safety-Related and Non Safety-Related Items in the Component Cooling Water System Room of the Qinshan Nuclear Power Plant in the Earthquake Condition

Liang Zhang, Gang Xu, Yue Wang, Li Chen, Shao Chong Zhou
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, V001T06A028, August 4–5, 2020
Paper No: ICONE2020-16825
DOI: https://doi.org/10.1115/ICONE2020-16825
View Paper titled, Study on the Interaction Between Safety-Related and Non Safety-Related Items in the Component Cooling Water System Room of the Qinshan Nuclear Power Plant in the Earthquake Condition
Click here to open pdf in another window PDF for Study on the Interaction Between Safety-Related and Non Safety-Related Items in the Component Cooling Water System Room of the Qinshan Nuclear Power Plant in the Earthquake Condition
Topics: Cooling, Earthquakes, Nuclear power stations, Pipes, Safety, Valves, Water