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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89580
https://doi.org/10.1115/ICONE29-89580
View Paper titled, Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94477
https://doi.org/10.1115/ICONE29-94477
View Paper titled, Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding
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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
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

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
Publisher: American Society of Mechanical Engineers
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
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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
Publisher: American Society of Mechanical Engineers
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
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Topics: Ships, Small modular reactors, Spent fuel storage, Storage, Accidents, Boron, Deformation, Fuel storage, Fuels, Accounting
Proceedings Papers

Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident

Fenglong Wang, Xuanlan Mei, Liang Zhang, Yong Yang, Qiang Zhang, Shixi Wang, Mingyu Wu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91511
https://doi.org/10.1115/ICONE29-91511
View Paper titled, Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident
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Topics: Accidents, Central heating, Damage, Fuels, China, Design, Background radiation, Emergency management, Hazard analysis, Radioactive substances
Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93244
https://doi.org/10.1115/ICONE29-93244
View Paper titled, Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model
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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)
Proceedings Papers

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

Xiaolin Chen, Simon Li, Songbai Cheng
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92109
https://doi.org/10.1115/ICONE29-92109
View Paper titled, Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code
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Topics: Accidents, Flow (Dynamics), Sodium fast reactors, Three-dimensional models, Transients (Dynamics)
Proceedings Papers

Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate

Zhipeng Wang, Changwu Wang, Qian Sun, Yuhang Zhang, Lei Chen
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A066, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93641
https://doi.org/10.1115/ICONE29-93641
View Paper titled, Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate
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Topics: Radiation (Physics), Radioactive substances, Safety, Transportation systems, Regulations, Containers, Accidents, Biomedicine, China, Pollution
Proceedings Papers

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91812
https://doi.org/10.1115/ICONE29-91812
View Paper titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications
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Topics: Accidents, Fast neutron reactors, Sodium fast reactors