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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

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022
Paper No: ICONE29-89165
DOI: https://doi.org/10.1115/ICONE29-89165
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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design
Proceedings Papers

Reliability Analysis of Off-Plant Power for Multi-Units

Chen Honghao, Ren Cheng, Wu Jian, Liu Deyi, Luo Yang, Zou Shengjia, Wang Zilong
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A024, August 8–12, 2022
Paper No: ICONE29-91870
DOI: https://doi.org/10.1115/ICONE29-91870
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Topics: Accidents, Emergencies, Event history analysis, Failure, Modeling, Nuclear power, Nuclear power stations, Power grids, Probabilistic safety assessment, Reliability
Proceedings Papers

Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method

Zehua Ma, Ren Liang, Zhikang Lin, Yong Ouyang, Xianghui Lu, Guanghui Su
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A029, August 8–12, 2022
Paper No: ICONE29-91377
DOI: https://doi.org/10.1115/ICONE29-91377
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Topics: Accidents, Computer simulation, Coolants, Discrete element methods, Fuels
Proceedings Papers

Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

Hua Zheng, Shuhong Wei
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A037, August 8–12, 2022
Paper No: ICONE29-92239
DOI: https://doi.org/10.1115/ICONE29-92239
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Topics: Design, Feedback, Vessels, Nuclear power stations, Safety, Accident management, Accidents, Construction, Control panels, Control rooms
Proceedings Papers

Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

Zhang Xingzhen, Sun Hui, Zhao Yanjun, Shi Xianzuo
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A056, August 8–12, 2022
Paper No: ICONE29-92834
DOI: https://doi.org/10.1115/ICONE29-92834
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Topics: Excitation, Excitation systems, Nuclear power stations, Simulation, Bridges (Structures), Maintenance, Failure, Nuclear power, Accidents, Construction
Proceedings Papers

Criticality Safety Analysis of Fuel Storage Under Fuel Assembly Dropping Accident

Mingliang Dai, Pengtao Fu, Jun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A013, August 8–12, 2022
Paper No: ICONE29-90509
DOI: https://doi.org/10.1115/ICONE29-90509
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Topics: Accidents, Fuel storage, Fuels, Manufacturing, Safety
Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022
Paper No: ICONE29-90521
DOI: https://doi.org/10.1115/ICONE29-90521
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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors
Proceedings Papers

Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding

Lin Qin
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A009, August 8–12, 2022
Paper No: ICONE29-89580
DOI: https://doi.org/10.1115/ICONE29-89580
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Topics: Accidents, Cladding systems (Building), Nuclear fuels, Zirconium alloys
Proceedings Papers

Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions

Guangdong Liu, Weiliang Wu, He Zhu, Qingjun Ma, Qipeng Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A042, August 8–12, 2022
Paper No: ICONE29-91927
DOI: https://doi.org/10.1115/ICONE29-91927
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Topics: Accidents, Spent nuclear fuels, Stress, Transportation systems
Proceedings Papers

Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity

Linyuan Lu, LiHua Guo, Yajuan Zhong, Feng Zhang, Jun Lin
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A040, August 8–12, 2022
Paper No: ICONE29-91804
DOI: https://doi.org/10.1115/ICONE29-91804
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Topics: Composite materials, Computer simulation, Fuels, Silicon, Temperature distribution, Thermal conductivity, Thermal resistance, Uranium, Finite element methods, Accidents
Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022
Paper No: ICONE29-90736
DOI: https://doi.org/10.1115/ICONE29-90736
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Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants
Proceedings Papers

Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR

Yuxuan Liang, Xiang Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A068, August 8–12, 2022
Paper No: ICONE29-92887
DOI: https://doi.org/10.1115/ICONE29-92887
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Topics: Accidents, Fuels, Sensitivity analysis, Uncertainty analysis
Proceedings Papers

Feasibility Verification of One Operator Monitoring Two NSSS Modules in Power Plant With Six High Temperature Gas Cooled Reactors Under Accident Conditions

Runfa Miao, Qianqian Jia, Duo Li
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A001, August 8–12, 2022
Paper No: ICONE29-88953
DOI: https://doi.org/10.1115/ICONE29-88953
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Topics: Accidents, Gas cooled reactors, High temperature, Power stations
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

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

William A. Byers, Guoqiang Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A094, August 8–12, 2022
Paper No: ICONE29-94477
DOI: https://doi.org/10.1115/ICONE29-94477
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Topics: Cladding systems (Building), Zirconium, Corrosion, Coating processes, Coatings, Fuels, Pressurized water reactors, Accidents, Boiling, Boron
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

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Hidemasa Yamano, Shigenobu Kubo, Taro Kan, Akihiro Shibata, Edouard Hourcade, Jean François Dirat
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022
Paper No: ICONE29-91505
DOI: https://doi.org/10.1115/ICONE29-91505
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Topics: Accidents, Sodium fast reactors, Design, Coolants, Fuels, Probability, Sodium, Vessels
Proceedings Papers

Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor

Yaoxin Ye, Jun Zhao, Yunfei Xu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 8–12, 2022
Paper No: ICONE29-93407
DOI: https://doi.org/10.1115/ICONE29-93407
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Topics: Ships, Small modular reactors, Spent fuel storage, Storage, Accidents, Boron, Deformation, Fuel storage, Fuels, Accounting
Proceedings Papers

Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

Chong Qin, Kefan Zhang, Wenpei Feng, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A065, August 8–12, 2022
Paper No: ICONE29-92114
DOI: https://doi.org/10.1115/ICONE29-92114
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Topics: Accidents, Boilers, Fast neutron reactors, Pressure, Rupture, Waves