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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

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

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
Paper No: ICONE29-93277
DOI: https://doi.org/10.1115/ICONE29-93277
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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

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

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

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

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
Proceedings Papers

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

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
Paper No: ICONE29-91237
DOI: https://doi.org/10.1115/ICONE29-91237
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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

Li Tianbin, Ma Lin
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A009, August 8–12, 2022
Paper No: ICONE29-90741
DOI: https://doi.org/10.1115/ICONE29-90741
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Topics: Engines, Industrial research, Motors, Nuclear power stations, Nuclear reactor coolants, Pumps, Winding (process)
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

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

Xiaowei Jin, Naihua Wang, Xiangyu Chi
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A054, August 8–12, 2022
Paper No: ICONE29-91801
DOI: https://doi.org/10.1115/ICONE29-91801
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Topics: Boron, Flow (Dynamics), Nozzles, Water, Density, Errors, Nuclear reactor coolants
Proceedings Papers

Study on Interfacing System LOCA of VVER-1200

Jinyan Du, Fangyu Dong, Chao Ma
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A008, August 8–12, 2022
Paper No: ICONE29-89803
DOI: https://doi.org/10.1115/ICONE29-89803
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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
Proceedings Papers

The Numerical Method Research for Simulating the SMR Steady-State Primary System Flow and Head Loss

Zhongying Ma, Ge Li, Ting Wang, Jinggang Li
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A007, August 8–12, 2022
Paper No: ICONE29-92987
DOI: https://doi.org/10.1115/ICONE29-92987
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Topics: Flow (Dynamics), Numerical analysis, Steady state, Pressure, Design, Nuclear reactor coolants, Finite element analysis, Finite element methods, Hydraulics
Proceedings Papers

The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant

Zilong Wang, Deyi Liu, Ming Zhao, Li Wang, Jie Xu
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, V003T13A004, August 4–6, 2021
Paper No: ICONE28-64423
DOI: https://doi.org/10.1115/ICONE28-64423
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Topics: Design, Heat shielding, Nuclear power stations, Nuclear reactor coolants, Pumps, Safety
Proceedings Papers

Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on OPTIMUS

Yuan Yanli, Ye Xianhui, Li Lijuan, Yuan Feng
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A002, August 4–5, 2020
Paper No: ICONE2020-16485
DOI: https://doi.org/10.1115/ICONE2020-16485
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Topics: Nuclear reactor coolants, Sensitivity analysis
Proceedings Papers

Research on Fault Diagnosis of Reactor Coolant Accident in Nuclear Power Plant Based on Radial Basis Function and Fuzzy Neural Network

Pengpeng Sun, Yong Liu, Guohua Wu, Zhiyong Duan
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, V001T06A005, August 4–5, 2020
Paper No: ICONE2020-16138
DOI: https://doi.org/10.1115/ICONE2020-16138
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Topics: Accidents, Artificial neural networks, Fault diagnosis, Fuzzy logic, Fuzzy neural nets, Nuclear power stations, Nuclear reactor coolants, Safety
Proceedings Papers

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Antony M. Hurst, Pavitra Bansal
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, V001T06A016, August 4–5, 2020
Paper No: ICONE2020-16474
DOI: https://doi.org/10.1115/ICONE2020-16474
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Topics: Finite element methods, Pipes, Underpinning, Hinges, Design, Finite element analysis, Light water reactors, Nuclear power stations, Nuclear reactor coolants, Stress
Proceedings Papers

Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

Cai Zhiyun, Ren Yun, Lai Jianyong, Zhang Yulong, Liu Hang, Liu Xianghong, Liu Minghao, Ye Zhu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A007, August 4–5, 2020
Paper No: ICONE2020-16341
DOI: https://doi.org/10.1115/ICONE2020-16341
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Topics: Equilibrium (Physics), Simulation analysis, Transients (Dynamics), Flow (Dynamics), Nuclear reactor coolants, Pressure, Safety, Valves, Water, Boundary-value problems
Proceedings Papers

Study on the Shaking Dynamic Response of Steam Generator LOCA

Qian Huang, Xiaofei Yu, Huanhuan Qi, Naibin Jiang, Fengchun Cai, Zhipeng Feng
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A009, July 22–26, 2018
Paper No: ICONE26-81278
DOI: https://doi.org/10.1115/ICONE26-81278
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Topics: Boilers, Dynamic response, Dynamic response analysis, Nuclear power stations, Nuclear reactor coolants, Stress, Accidents, China, Computational methods, Coolants
Proceedings Papers

Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator

Feng-chun Cai, Xian-hui Ye, Qian Huang, Wenzheng Zhang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A010, July 22–26, 2018
Paper No: ICONE26-81279
DOI: https://doi.org/10.1115/ICONE26-81279
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Topics: Boilers, Failure, Probability, Stress, Nonlinear systems, Nuclear reactor coolants, Plasticity, Safety, Seismic analysis, Stress analysis (Engineering)