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Proceedings Papers

Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

Yuichi Onoda, Masato Uchita, Minako Tokizaki, Hitoshi Okazaki

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A016, August 8–12, 2022

Paper No: ICONE29-91688

DOI: https://doi.org/10.1115/ICONE29-91688

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Topics: Pumps, Rupture, Safety, Signals, Sodium fast reactors

Proceedings Papers

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Donghao Li, Daogang Lu, Yuxuan Zhu, Yu Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A032, August 8–12, 2022

Paper No: ICONE29-92137

DOI: https://doi.org/10.1115/ICONE29-92137

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Topics: Fluid structure interaction, Pipes, Shells, Vibration, Finite element model, Fluids, Water, Computer software, Fast neutron reactors, Heat shielding

Proceedings Papers

Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net

Jinchao Liu, Yaozu Lin, Bijun Chen, Xue Lyu, Jiayi Li, Heng Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A044, August 8–12, 2022

Paper No: ICONE29-92540

DOI: https://doi.org/10.1115/ICONE29-92540

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Topics: Nuclear power, Pumps, Simulation, Stress

Proceedings Papers

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Chaofan Zhang, Daogang Lu, Yu Liu, Haotian Qiu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A036, August 8–12, 2022

Paper No: ICONE29-92274

DOI: https://doi.org/10.1115/ICONE29-92274

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Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)

Proceedings Papers

Review on Reactor Coolant Pumps Trip Criteria After Small Break LOCA in PWR

Zhenying Jiao, Zhenying Wang, Yu Huang, Liu Liu, Taike Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A017, August 8–12, 2022

Paper No: ICONE29-91395

DOI: https://doi.org/10.1115/ICONE29-91395

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Topics: Cooling, Nuclear reactor coolants, Pressurized water reactors, Pumps

Proceedings Papers

The Comprehensive Performance Comparison Research Between Two Types of Radiators Applied in Electronic Equipment

Chonghai Huang, Yelei Zhang, Xiaohu Yang, Hanbing Ke, Qi Xiao

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A001, August 8–12, 2022

Paper No: ICONE29-88784

DOI: https://doi.org/10.1115/ICONE29-88784

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Topics: Electronic equipment, Microchannels, Pumps, Water

Proceedings Papers

Thermal Performance Monitoring and Analysis of Nuclear Power Plant

Jianfei Hou, Xun Zhang, Heino Zimmermann, Zhaohui Xiang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A011, August 8–12, 2022

Paper No: ICONE29-91886

DOI: https://doi.org/10.1115/ICONE29-91886

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Topics: Nuclear power stations, Instrumentation, Circuits, Computer software, Condensers (steam plant), Damage, Design, Feedwater, High pressure (Physics), Pressure

Proceedings Papers

Research on Cold End Optimization of Water Supply Mode of Expanded Unit System of Circulating Water System in Coastal Nuclear Power Plant

Fang Lin, Jiale Jian, Fang Wang, Jia Yang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A024, August 8–12, 2022

Paper No: ICONE29-92613

DOI: https://doi.org/10.1115/ICONE29-92613

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Topics: Cooling, Machinery, Nuclear power stations, Optimization, Pumps, Shorelines, Steam turbines, Water, Water supply

Proceedings Papers

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

Zhiming Wu, Yixin Ling, Xing Liu, Dongdong Fei, Xiaoyu Hou, Xue Wen

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A078, August 8–12, 2022

Paper No: ICONE29-93343

DOI: https://doi.org/10.1115/ICONE29-93343

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Topics: Corrosion, Feedwater, Pipes, Pumps

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

Paper No: ICONE29-91638

DOI: https://doi.org/10.1115/ICONE29-91638

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Topics: Condition monitoring, Fault diagnosis, Maintenance, Monitoring systems, Nuclear power stations, Pattern recognition, Economics , Safety, Carbon, Construction

Proceedings Papers

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

Zhang Hengrui, Huang Qian, Fu Peiren, Zhang Daoke, Cai Rui, Sun Lei, Chen Qiuyang, Xue Feng

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A050, August 8–12, 2022

Paper No: ICONE29-92727

DOI: https://doi.org/10.1115/ICONE29-92727

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Topics: Damage, Nuclear reactor coolants, Pumps

Proceedings Papers

Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump

Yun Zhong

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A075, August 8–12, 2022

Paper No: ICONE29-93302

DOI: https://doi.org/10.1115/ICONE29-93302

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Topics: Design, Fluids, Inertia (Mechanics), Nuclear reactor coolants, Pumps

Proceedings Papers

Design Verification of Minimum Flow Valve of the Main Feed Water Pump Based on the Full-Range Simulation Platform of CPR 1000

Zhenhua Zhang, Bo Zhang, Chaoying Zheng

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A014, August 8–12, 2022

Paper No: ICONE29-90543

DOI: https://doi.org/10.1115/ICONE29-90543

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Topics: Design, Feedwater, Flow (Dynamics), Pumps, Simulation, Valves

Proceedings Papers

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Wei Li, Jianfeng Shi, Yulong Qin, Lihua Wang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A047, August 8–12, 2022

Paper No: ICONE29-92633

DOI: https://doi.org/10.1115/ICONE29-92633

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Topics: Feedwater, Pumps, Rods, Nuclear power stations, Turbines

Proceedings Papers

Experimental Study on Pressure Pulsation of RCP With Steam Generator

Song Huang, Yu Song, Junlian Yin, Rui Xu, Dezhong Wang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A081, August 8–12, 2022

Paper No: ICONE29-93423

DOI: https://doi.org/10.1115/ICONE29-93423

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Topics: Boilers, Nuclear reactor coolants, Pressure, Pumps

Proceedings Papers

Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II

Canxing Huang, Huasheng Xiong, Junting Feng

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A014, August 8–12, 2022

Paper No: ICONE29-91509

DOI: https://doi.org/10.1115/ICONE29-91509

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Topics: Accidents, Boilers, Control systems, Coolants, Heating, Nuclear power, Pressurized water reactors, Pumps, Radioactivity, Safety

Proceedings Papers

Research and Treatment of Periodic Fluctuation of Steam Feed Pump Speed Regarding 900MW Nuclear Power Plant

Heng Li, Xiaoyu Liu, Xufeng Wang

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A028, August 8–12, 2022

Paper No: ICONE29-92865

DOI: https://doi.org/10.1115/ICONE29-92865

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Topics: Nuclear power stations, Pumps, Steam

Proceedings Papers

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022

Paper No: ICONE29-91821

DOI: https://doi.org/10.1115/ICONE29-91821

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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting

Proceedings Papers

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Xinyue Luo, Daogang Lu, Jiaqi Feng, Yuhao Zhang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A040, August 8–12, 2022

Paper No: ICONE29-92323

DOI: https://doi.org/10.1115/ICONE29-92323

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Topics: Heat transfer, Radiation (Physics), Sodium fast reactors, Cavities, Fast neutron reactors, Temperature, Vessels, Computational fluid dynamics, Construction, Containers

Proceedings Papers

Research on the Effect of Non-Uniform Inflow on the Cavitation Characteristics of the RCP

Yu Song, Song Huang, Rui Xu, Junlian Yin, Dezhong Wang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A061, August 8–12, 2022

Paper No: ICONE29-93342

DOI: https://doi.org/10.1115/ICONE29-93342

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Topics: Cavitation, Inflow, Nuclear reactor coolants, Pumps

2 3 4 5

NARROW

Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Review on Reactor Coolant Pumps Trip Criteria After Small Break LOCA in PWR

The Comprehensive Performance Comparison Research Between Two Types of Radiators Applied in Electronic Equipment

Thermal Performance Monitoring and Analysis of Nuclear Power Plant

Research on Cold End Optimization of Water Supply Mode of Expanded Unit System of Circulating Water System in Coastal Nuclear Power Plant

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

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

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump

Design Verification of Minimum Flow Valve of the Main Feed Water Pump Based on the Full-Range Simulation Platform of CPR 1000

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Experimental Study on Pressure Pulsation of RCP With Steam Generator

Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II

Research and Treatment of Periodic Fluctuation of Steam Feed Pump Speed Regarding 900MW Nuclear Power Plant

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Research on the Effect of Non-Uniform Inflow on the Cavitation Characteristics of the RCP

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