1-20 of 1607
Accidents
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor

Rong Liu, Huiyun Han, Shengyu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A068, August 8–12, 2022
Paper No: ICONE29-91980
https://doi.org/10.1115/ICONE29-91980
View Paper titled, Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor
Open the PDF for Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor in another window
Topics: Accidents, Cladding systems (Building), Fuels, Light water reactors
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
https://doi.org/10.1115/ICONE29-93277
View Paper titled, Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation
Open the PDF for Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation in another window
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
https://doi.org/10.1115/ICONE29-89165
View Paper titled, Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
Open the PDF for Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents in another window
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
https://doi.org/10.1115/ICONE29-91870
View Paper titled, Reliability Analysis of Off-Plant Power for Multi-Units
Open the PDF for Reliability Analysis of Off-Plant Power for Multi-Units in another window
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
https://doi.org/10.1115/ICONE29-91377
View Paper titled, Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method
Open the PDF for Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method in another window
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
https://doi.org/10.1115/ICONE29-92239
View Paper titled, Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention
Open the PDF for Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention in another window
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
https://doi.org/10.1115/ICONE29-92834
View Paper titled, Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant
Open the PDF for Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant in another window
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
https://doi.org/10.1115/ICONE29-90509
View Paper titled, Criticality Safety Analysis of Fuel Storage Under Fuel Assembly Dropping Accident
Open the PDF for Criticality Safety Analysis of Fuel Storage Under Fuel Assembly Dropping Accident in another window
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
https://doi.org/10.1115/ICONE29-90521
View Paper titled, Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition
Open the PDF for Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition in another window
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
https://doi.org/10.1115/ICONE29-89580
View Paper titled, Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding
Open the PDF for Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding in another window
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
https://doi.org/10.1115/ICONE29-91927
View Paper titled, Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions
Open the PDF for Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions in another window
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
https://doi.org/10.1115/ICONE29-91804
View Paper titled, Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity
Open the PDF for Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity in another window
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
https://doi.org/10.1115/ICONE29-90736
View Paper titled, Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors
Open the PDF for Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors in another window
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
https://doi.org/10.1115/ICONE29-92887
View Paper titled, Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR
Open the PDF for Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR in another window
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
https://doi.org/10.1115/ICONE29-88953
View Paper titled, Feasibility Verification of One Operator Monitoring Two NSSS Modules in Power Plant With Six High Temperature Gas Cooled Reactors Under Accident Conditions
Open the PDF for Feasibility Verification of One Operator Monitoring Two NSSS Modules in Power Plant With Six High Temperature Gas Cooled Reactors Under Accident Conditions in another window
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
https://doi.org/10.1115/ICONE29-91509
View Paper titled, Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II
Open the PDF for Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II in another window
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
https://doi.org/10.1115/ICONE29-94477
View Paper titled, Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding
Open the PDF for Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding in another window
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
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
Open the PDF for Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions in another window
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
https://doi.org/10.1115/ICONE29-91505
View Paper titled, Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor
Open the PDF for Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor in another window
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
https://doi.org/10.1115/ICONE29-93407
View Paper titled, Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor
Open the PDF for Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor in another window
Topics: Ships, Small modular reactors, Spent fuel storage, Storage, Accidents, Boron, Deformation, Fuel storage, Fuels, Accounting