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Proceedings Papers

Study on Long-Life Minor Actinide Temporary Storage Scheme Based on High-Level Liquid Waste Partitioning Strategy

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Xiantao Meng, Meng Wei
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A043, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135666
https://doi.org/10.1115/ICONE31-135666
View Paper titled, Study on Long-Life Minor Actinide Temporary Storage Scheme Based on High-Level Liquid Waste Partitioning Strategy
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Topics: Storage
Proceedings Papers

Study on the Development Path of AFR Storage for Spent Fuel in China

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Lei Shi, Haoran Lu, Yihan Wang, Jian Hu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A051, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136022
https://doi.org/10.1115/ICONE31-136022
View Paper titled, Study on the Development Path of AFR Storage for Spent Fuel in China
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Topics: China, Construction, Spent nuclear fuels, Storage
Proceedings Papers

The SPIZWURZ Project - Experimental and Modeling Approaches of Hydrogen in Cladding Tubes Under Dry Storage Conditions

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Sarah Weick, Michel Herm, Mirco Grosse, Robert Kilger, Conrado Rössger, Martin Steinbrueck, Juri Stuckert
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A064, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136905
https://doi.org/10.1115/ICONE31-136905
View Paper titled, The SPIZWURZ Project - Experimental and Modeling Approaches of Hydrogen in Cladding Tubes Under Dry Storage Conditions
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Topics: Cladding systems (Building), Hydrogen, Modeling, Storage
Proceedings Papers

CFD-DEM Simulation on Gas-Solid Separation and Sphere Packing Behaviors in a Storage Bin of the Small Absorber Sphere System

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Tianjin Li, Haitao Hu, He Yan, Xingzhong Diao
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A054, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135598
https://doi.org/10.1115/ICONE31-135598
View Paper titled, CFD-DEM Simulation on Gas-Solid Separation and Sphere Packing Behaviors in a Storage Bin of the Small Absorber Sphere System
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Topics: Computational fluid dynamics, Discrete element methods, Flow (Dynamics), Packing (Shipments), Packings (Cushioning), Separation (Technology), Simulation, Storage, Very high temperature reactors
Proceedings Papers

Study on NUREG-2215 Regulatory Condition for Reflooding of the Previously Dried High Burnup Fuel Is Not Allowable During Dry Storage

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Ting-Yi Liao, Yi-Fan Tseng, Kuan-Che Lan, Wan-June Chiu, Hsiao-Ming Tung
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135819
https://doi.org/10.1115/ICONE31-135819
View Paper titled, Study on NUREG-2215 Regulatory Condition for Reflooding of the Previously Dried High Burnup Fuel Is Not Allowable During Dry Storage
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Topics: Cladding systems (Building), Fuels, Storage
Proceedings Papers

Scaled Experiment on Flow Characteristics of a Single Area of Spent Fuel Dry-Storage System of HTR-PM1000

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Jinhua Wang, Mengyao Wang, Menghang Gong, Yue Li, Bin Wu, Wei Zhang, Lihua Gao, Tao Ma, Haitao Wang, Bing Liu
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134632
https://doi.org/10.1115/ICONE31-134632
View Paper titled, Scaled Experiment on Flow Characteristics of a Single Area of Spent Fuel Dry-Storage System of HTR-PM1000
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Topics: Flow (Dynamics), Spent nuclear fuels, Storage
Proceedings Papers

Layers of Protection When Adapting Modern Technologies to Enable Remote Handling of Radioactive Materials

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Sohaib Syed
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133409
https://doi.org/10.1115/ICONE31-133409
View Paper titled, Layers of Protection When Adapting Modern Technologies to Enable Remote Handling of Radioactive Materials
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Topics: Radioactive substances, Design, Hazards, Radioactive wastes, Safety, Accidents, Containers, Defense industry, Nuclear decommissioning, Risk
Proceedings Papers

Design and Research of Radioactive Waste Gas Treatment System for Medical Isotope Test Reactor

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Zhang Yongkang, Zhang Jinsong, Yang Huiqing, Chen Li, Chen Yunming
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130479
https://doi.org/10.1115/ICONE31-130479
View Paper titled, Design and Research of Radioactive Waste Gas Treatment System for Medical Isotope Test Reactor
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Topics: Activated carbon, Biomedicine, Design, Hydrogen, Isotopes, Nitrogen oxides, Radioactive wastes, Storage, Half-life, Nuclides
Proceedings Papers

Development and Application of High Temperature and Radiation Protection Equipment for Spent Fuel Dry Storage System

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Cheng Cheng, Wei Yuanyuan, Pan Yongjie, Ge Yongjun, Wei Zhiguo, Zhou Zhihui, Li Zengfen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92083
https://doi.org/10.1115/ICONE29-92083
View Paper titled, Development and Application of High Temperature and Radiation Protection Equipment for Spent Fuel Dry Storage System
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Topics: High temperature, Radiation (Physics), Risk, Spent nuclear fuels, Storage
Proceedings Papers

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

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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

Scaling of Thermal and Flow Behavior in Dry Storage Casks for Nuclear Spent Fuel

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Qinglong Wen, Ting Yang, Shijia Xu, Zhengquan Wang, Bo Yuan
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89444
https://doi.org/10.1115/ICONE29-89444
View Paper titled, Scaling of Thermal and Flow Behavior in Dry Storage Casks for Nuclear Spent Fuel
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Topics: Flow (Dynamics), Spent nuclear fuels, Storage
Proceedings Papers

Numerical Simulation Study on Anti-Wave Problem of Fluid Storage in Pressurizer Under Marine Conditions

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Jinyu Yue, Tianyi Wei, Sijie Xu, Biao Zhang, Dongyang Li, Sichao Tan
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A068, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93853
https://doi.org/10.1115/ICONE29-93853
View Paper titled, Numerical Simulation Study on Anti-Wave Problem of Fluid Storage in Pressurizer Under Marine Conditions
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Topics: Computer simulation, Fluids, Storage, Waves
Proceedings Papers

Optimization Configuration and Design Considerations of Spent Fuel Storage and Transport Casks for Nuclear Power Plants in China

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Fengwu Liu, Shiyuan Li, Lijun Wang, Shunping Jing, Chao Liu, Xiaoqing Li
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92905
https://doi.org/10.1115/ICONE29-92905
View Paper titled, Optimization Configuration and Design Considerations of Spent Fuel Storage and Transport Casks for Nuclear Power Plants in China
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Topics: China, Design, Nuclear power stations, Optimization, Spent fuel storage, Spent nuclear fuels, Storage
Proceedings Papers

PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation

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Li Wen, Gao Jinghui, Li Gang, Zhong Shengdong, Xu Jin, Zhao Bingquan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A078, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93351
https://doi.org/10.1115/ICONE29-93351
View Paper titled, PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation
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Topics: Pressurized water reactors, Safety, Spent nuclear fuels, Storage
Proceedings Papers

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

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Nanfeng Cao, Shouhai Yang, Enfei Xie, Shunping Jing
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A077, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93332
https://doi.org/10.1115/ICONE29-93332
View Paper titled, Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly
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Topics: Manufacturing, Neutron sources, Safety, Storage, Transportation systems
Proceedings Papers

Construction and Application of Collaborative Editing System for the Nuclear Power Large Comprehensive Report

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Cheng Luo, Lin Jia, Wang Hao, Xiangyong Wu
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92900
https://doi.org/10.1115/ICONE29-92900
View Paper titled, Construction and Application of Collaborative Editing System for the Nuclear Power Large Comprehensive Report
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Topics: Construction, Nuclear power, Storage, Collaboration, Errors, Optimization, Process control, Workflow
Proceedings Papers

Development and Experiment on High Temperature and Radiation Resistance Concrete Material for Spent Fuel Dry Storage

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Zhang Xueling, Cheng Cheng, Pan Yongjie, Wei Yuanyuan, Tang Qionghui, Li Zengfen, Yang Shouhai
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A047, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92125
https://doi.org/10.1115/ICONE29-92125
View Paper titled, Development and Experiment on High Temperature and Radiation Resistance Concrete Material for Spent Fuel Dry Storage
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Topics: Concretes, Fibers, High temperature, Radiation (Physics), Spent nuclear fuels, Steel, Storage, Tension
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

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Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister

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Qionghui Tang, Mao-Yun Li, Cheng Cheng, En-Fei Xie
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92217
https://doi.org/10.1115/ICONE29-92217
View Paper titled, Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister
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Topics: Computational fluid dynamics, Spent nuclear fuels, Storage
Proceedings Papers

A MIN-TPN-Based Remote Disaster Recovery and Backup Scheme of Power Industrial Control System in Nuclear Power Plants

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Cui Gang, Xin Yang, Hui Li, Han Wang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91998
https://doi.org/10.1115/ICONE29-91998
View Paper titled, A MIN-TPN-Based Remote Disaster Recovery and Backup Scheme of Power Industrial Control System in Nuclear Power Plants
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Topics: Disaster recovery, Industrial controls, Nuclear power stations, Storage