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Proceedings Papers

Analysis of Water Hammer in the Reactor Coolant System Based on Wave Tracking Method

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Qianping Zhang, Shubiao Dong, Xiaoyu Zhang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134766
https://doi.org/10.1115/ICONE31-134766
View Paper titled, Analysis of Water Hammer in the Reactor Coolant System Based on Wave Tracking Method
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Topics: Nuclear reactor coolants, Pumps, Water hammer, Waves
Proceedings Papers

Research on Typical Fault Prediction Model of the Reactor Coolant Pump Based on Multi-Information Fusion of GRU

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Cui Huaiming, Kuang Chengxiao
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A038, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135905
https://doi.org/10.1115/ICONE31-135905
View Paper titled, Research on Typical Fault Prediction Model of the Reactor Coolant Pump Based on Multi-Information Fusion of GRU
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Topics: Nuclear reactor coolants, Pumps
Proceedings Papers

Key Technologies Research for the Implementation of In-Service Inspection Strategies Optimizing for the Reactor Coolant System of In-Service Nuclear Power Plants

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Yunhai Shen, Feng Deng, Yongqiang Duan, Xiaoquan Yu, Shuixiang Ye
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A019, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134982
https://doi.org/10.1115/ICONE31-134982
View Paper titled, Key Technologies Research for the Implementation of In-Service Inspection Strategies Optimizing for the Reactor Coolant System of In-Service Nuclear Power Plants
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Topics: Hydrostatic testing, In-service inspection, Nuclear power stations, Nuclear reactor coolants
Proceedings Papers

Predictions of Component Remaining Useful Life Using Bayesian LSTM for Reactor Coolant Pump

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Renyi Xu, Yan Wang, Minjun Peng, Huaiming Cui, Hang Wang, Chengxiao Kuang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135439
https://doi.org/10.1115/ICONE31-135439
View Paper titled, Predictions of Component Remaining Useful Life Using Bayesian LSTM for Reactor Coolant Pump
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Topics: Nuclear reactor coolants, Pumps, Service life (Equipment), Uncertainty
Proceedings Papers

Research on the Radiation Monitoring Methods in the Reactor Coolant Pressure Boundary Leakage of Nuclear Power Plant

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Zhenlei Yang, Chengmin Liu, Tianzhi Jiang, Jin Li, Xianglin Zhuo, Hongliang Zhu, Liang He, Zhengxi He, Jinqiu Peng
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130567
https://doi.org/10.1115/ICONE31-130567
View Paper titled, Research on the Radiation Monitoring Methods in the Reactor Coolant Pressure Boundary Leakage of Nuclear Power Plant
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Topics: Leakage, Nuclear power stations, Nuclear reactor coolants, Pressure, Radiation measurement
Proceedings Papers

Analysis of SMR Reactor Coolant System in APROS

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Zhu Ye, Wang Xinbo, Liao Xianwei, Cai Zhiyun, Liu Minghao
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131299
https://doi.org/10.1115/ICONE31-131299
View Paper titled, Analysis of SMR Reactor Coolant System in APROS
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Topics: Nuclear reactor coolants, Simulation
Proceedings Papers

Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method

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Mingqian Zhang, Run Lin
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132452
https://doi.org/10.1115/ICONE31-132452
View Paper titled, Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method
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Topics: Computational fluid dynamics, Coolants, Domes (Structural elements), Nuclear reactor coolants, Pressurized water reactors, Simulation, Swirling flow, Thermal hydraulics, Pumps, Reactor vessels
Proceedings Papers

Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000

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Zhengrun Shang, Dufeng Lv, Zhaoming Meng, Zhongning Sun
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135645
https://doi.org/10.1115/ICONE31-135645
View Paper titled, Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000
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Topics: Accidents, Containment, Cooling, Cooling systems, Design, Loss of coolant accidents, Nuclear reactor coolants, Pipelines, Pressure, Redundancy (Engineering)
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91395
https://doi.org/10.1115/ICONE29-91395
View Paper titled, Review on Reactor Coolant Pumps Trip Criteria After Small Break LOCA in PWR
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Topics: Cooling, Nuclear reactor coolants, Pressurized water reactors, Pumps
Proceedings Papers

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

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Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91821
https://doi.org/10.1115/ICONE29-91821
View Paper titled, Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions
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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting
Proceedings Papers

Experimental Study of the Outlet Boron Concentration Dynamic Characteristic of the Volume Control Tank in Boration Process

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Xiaowei Jin, Naihua Wang, Xiangyu Chi
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A054, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91801
https://doi.org/10.1115/ICONE29-91801
View Paper titled, Experimental Study of the Outlet Boron Concentration Dynamic Characteristic of the Volume Control Tank in Boration Process
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Topics: Boron, Flow (Dynamics), Nozzles, Water, Density, Errors, Nuclear reactor coolants
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93342
https://doi.org/10.1115/ICONE29-93342
View Paper titled, Research on the Effect of Non-Uniform Inflow on the Cavitation Characteristics of the RCP
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Topics: Cavitation, Inflow, Nuclear reactor coolants, Pumps
Proceedings Papers

Analytical and Experimental Research on Reactor Coolant Pump Mechanical Seals With Hydrodynamic Deep-Grooves

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Liming Tang, Yongchun Pan, Xin Tan, Le Jin, Yan Wang
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91237
https://doi.org/10.1115/ICONE29-91237
View Paper titled, Analytical and Experimental Research on Reactor Coolant Pump Mechanical Seals With Hydrodynamic Deep-Grooves
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Topics: Leakage, Nuclear reactor coolants, Pressure, Pumps
Proceedings Papers

Research and Development of Wet Winding Motor Reactor Coolant Pump for Generation 3 Nuclear Power Plant

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Li Tianbin, Ma Lin
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90741
https://doi.org/10.1115/ICONE29-90741
View Paper titled, Research and Development of Wet Winding Motor Reactor Coolant Pump for Generation 3 Nuclear Power Plant
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Topics: Engines, Industrial research, Motors, Nuclear power stations, Nuclear reactor coolants, Pumps, Winding (process)
Proceedings Papers

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

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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

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92727
https://doi.org/10.1115/ICONE29-92727
View Paper titled, Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump
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Topics: Damage, Nuclear reactor coolants, Pumps
Proceedings Papers

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

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Dongyuan Li, Jinkai Wang, Jiaoshen Xu, Zengpei Zhu, Yaqi Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A072, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93277
https://doi.org/10.1115/ICONE29-93277
View Paper titled, Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation
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Topics: Nuclear power plant operations, Nuclear reactor coolants, Nucleate boiling, Safety, Accidents, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Feedwater, Steam
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93302
https://doi.org/10.1115/ICONE29-93302
View Paper titled, Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump
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Topics: Design, Fluids, Inertia (Mechanics), Nuclear reactor coolants, Pumps
Proceedings Papers

Experimental Study on Pressure Pulsation of RCP With Steam Generator

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93423
https://doi.org/10.1115/ICONE29-93423
View Paper titled, Experimental Study on Pressure Pulsation of RCP With Steam Generator
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Topics: Boilers, Nuclear reactor coolants, Pressure, Pumps
Proceedings Papers

Study on Interfacing System LOCA of VVER-1200

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Jinyan Du, Fangyu Dong, Chao Ma
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89803
https://doi.org/10.1115/ICONE29-89803
View Paper titled, Study on Interfacing System LOCA of VVER-1200
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Topics: Accidents, Containment, Coolants, Damage, Defense industry, Emergency core cooling systems, High pressure (Physics), Nuclear power stations, Nuclear reactor coolants, Pressure