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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

Paper No: ICONE29-93641

DOI: https://doi.org/10.1115/ICONE29-93641

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Topics: Radiation (Physics), Radioactive substances, Safety, Transportation systems, Regulations, Containers, Accidents, Biomedicine, China, Pollution

Proceedings Papers

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

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

Paper No: ICONE29-93332

DOI: https://doi.org/10.1115/ICONE29-93332

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Topics: Manufacturing, Neutron sources, Safety, Storage, Transportation systems

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

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

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

Paper No: ICONE29-89241

DOI: https://doi.org/10.1115/ICONE29-89241

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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

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

Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants

Jiqiang Su, Qun Liu, Honglin Zhang, Lei Shi, Hongjun Liu, Yanrui Li, Jian Hu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A062, August 8–12, 2022

Paper No: ICONE29-92757

DOI: https://doi.org/10.1115/ICONE29-92757

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Topics: Nuclear power stations, Spent nuclear fuels, Transportation systems

Proceedings Papers

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Jinhua Wang, Yuchen Hao, Yue Li, Bin Wu, Haitao Wang, Tao Ma

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A002, August 4–6, 2021

Paper No: ICONE28-63134

DOI: https://doi.org/10.1115/ICONE28-63134

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Topics: Fuels, Gas cooled reactors, High temperature, Nuclear power, Transportation systems

Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg

Paper No: ICONE28-65765

DOI: https://doi.org/10.1115/ICONE28-65765

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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics

Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang

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, V003T11A007, August 4–6, 2021

Paper No: ICONE28-63388

DOI: https://doi.org/10.1115/ICONE28-63388

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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics

Proceedings Papers

Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask

Yuchen Hao, Jinhua Wang, Yue Li, Bin Wu, Haitao Wang, Tao Ma

Paper No: ICONE28-63369

DOI: https://doi.org/10.1115/ICONE28-63369

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Topics: Nuclear power, Optimization, Spent nuclear fuels, Transportation systems

Proceedings Papers

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

Wen Yang, Xing Li, Jinrong Qiu, Lun Zhou

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A042, August 4–6, 2021

Paper No: ICONE28-64457

DOI: https://doi.org/10.1115/ICONE28-64457

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Topics: Containers, Pressurized water reactors, Radiation (Physics), Spent fuel storage, Spent nuclear fuels, Transportation systems

Proceedings Papers

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

Edward M. Duchnowski, Seokbin Seo, Nicholas R. Brown

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A046, August 4–5, 2020

Paper No: ICONE2020-16812

DOI: https://doi.org/10.1115/ICONE2020-16812

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Topics: Cladding systems (Building), Spent nuclear fuels, Storage, Transportation systems, Uncertainty quantification, Hydrogen, Diffusion (Physics), Fuels, Temperature profiles, Uncertainty

Proceedings Papers

Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

Hector Mendoza, Victor G. Figueroa, Walter Gill, Scott Sanborn

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A054, August 4–5, 2020

Paper No: ICONE2020-16755

DOI: https://doi.org/10.1115/ICONE2020-16755

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Topics: Accidents, Filters, Fire, Liquid pool fires, Radiant heat, Radioactive substances, Safety, Stress, Testing, Thermogravimetry

Proceedings Papers

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A035, July 22–26, 2018

Paper No: ICONE26-81551

DOI: https://doi.org/10.1115/ICONE26-81551

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Topics: Sodium fast reactors, Thermal stratification, Turbulence, Sodium, Momentum, Breeder reactors, Buoyancy, Convection, Deformation, Diffusion (Physics)

Proceedings Papers

Research on Optimization of Ingestion Emergency Planning Zone Sizing

Mengxi Wang, Na Xue, Xinjian Liu

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A010, July 22–26, 2018

Paper No: ICONE26-81285

DOI: https://doi.org/10.1115/ICONE26-81285

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Topics: Emergency management, Optimization, Food products, Chain, Radioisotopes, Emergency preparedness, Plumes (Fluid dynamics), Contamination, Nuclear power stations, Simulation

Proceedings Papers

Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation

Zhen-Yu Hung, Pei-Hsun Huang, Chao-Jen Li

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A004, July 22–26, 2018

Paper No: ICONE26-81074

DOI: https://doi.org/10.1115/ICONE26-81074

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Topics: Safety, Transportation systems, Computer software, Containment, Corrective actions, Design, Emergency core cooling systems, Experimental analysis, Licensing, Nuclear power plant operations

Proceedings Papers

Research on the Influence of Complex Terrain on Atmospheric Dispersion After Accident

Nan Wu, Na Xue, Xinjian Liu

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A012, July 22–26, 2018

Paper No: ICONE26-81378

DOI: https://doi.org/10.1115/ICONE26-81378

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Topics: Accidents, Computational fluid dynamics, Computer software, Emergencies, Evacuations, Flow (Dynamics), Lakes, Modeling, Nuclear power stations, Nuclides

Proceedings Papers

On the Use of Robust Command Shaping for Vibration Reduction During Remote Handling of Large Components in Tokamak Devices

Stanislao Grazioso, Giuseppe Di Gironimo

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A015, July 22–26, 2018

Paper No: ICONE26-82346

DOI: https://doi.org/10.1115/ICONE26-82346

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Topics: Tokamaks, Vibration, Vessels, Engineering simulation, Simulation, Maintenance, Nuclear fusion, Shapes, Stress, Transients (Dynamics)

Proceedings Papers

We Never Built Small Modular Reactors (SMRs), but What Do We Know About Modularization in Construction?

Benito Mignacca, Giorgio Locatelli, Mahmoud Alaassar, Diletta Colette Invernizzi

Paper No: ICONE26-81604

DOI: https://doi.org/10.1115/ICONE26-81604

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Topics: Construction, Small modular reactors, Compression, Cost benefit analysis, Nuclear construction, Project management, Transportation systems

Proceedings Papers

Finite Element Analysis for Fuel Assembly Structural Behavior

Youngik Yoo, Kyounghong Kim, Kyongbo Eom, Seongki Lee, Jongsung Yoo

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A030, July 22–26, 2018

Paper No: ICONE26-81621

DOI: https://doi.org/10.1115/ICONE26-81621

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Topics: Finite element analysis, Fuels, Manufacturing, Accidents, Computer software, Failure mechanisms, Finite element model, Mechanical behavior, Mechanical testing, Radioactive substances

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NARROW

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

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

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

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

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

Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

A Sodium-Cooled Thermal-Spectrum Fission Battery

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Research on Optimization of Ingestion Emergency Planning Zone Sizing

Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation

Research on the Influence of Complex Terrain on Atmospheric Dispersion After Accident

On the Use of Robust Command Shaping for Vibration Reduction During Remote Handling of Large Components in Tokamak Devices

We Never Built Small Modular Reactors (SMRs), but What Do We Know About Modularization in Construction?

Finite Element Analysis for Fuel Assembly Structural Behavior

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