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Proceedings Papers

PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation

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

Paper No: ICONE29-93351

DOI: https://doi.org/10.1115/ICONE29-93351

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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

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

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

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

Paper No: ICONE29-92125

DOI: https://doi.org/10.1115/ICONE29-92125

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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

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

Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister

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

Paper No: ICONE29-92217

DOI: https://doi.org/10.1115/ICONE29-92217

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Topics: Computational fluid dynamics, Spent nuclear fuels, Storage

Proceedings Papers

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

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

Paper No: ICONE29-92083

DOI: https://doi.org/10.1115/ICONE29-92083

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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

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

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

Paper No: ICONE29-93853

DOI: https://doi.org/10.1115/ICONE29-93853

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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

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

Paper No: ICONE29-92905

DOI: https://doi.org/10.1115/ICONE29-92905

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Topics: China, Design, Nuclear power stations, Optimization, Spent fuel storage, Spent nuclear fuels, Storage

Proceedings Papers

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

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

Paper No: ICONE29-92900

DOI: https://doi.org/10.1115/ICONE29-92900

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Topics: Construction, Nuclear power, Storage, Collaboration, Errors, Optimization, Process control, Workflow

Proceedings Papers

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

Cui Gang, Xin Yang, Hui Li, Han Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A030, August 8–12, 2022

Paper No: ICONE29-91998

DOI: https://doi.org/10.1115/ICONE29-91998

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Topics: Disaster recovery, Industrial controls, Nuclear power stations, Storage

Proceedings Papers

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

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

Paper No: ICONE29-89444

DOI: https://doi.org/10.1115/ICONE29-89444

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Topics: Flow (Dynamics), Spent nuclear fuels, Storage

Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022

Paper No: ICONE29-91275

DOI: https://doi.org/10.1115/ICONE29-91275

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Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications

Proceedings Papers

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

Charles Forsberg, Daniel Stack, Patrick McDaniel

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, V001T02A028, August 4–6, 2021

Paper No: ICONE28-64638

DOI: https://doi.org/10.1115/ICONE28-64638

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Topics: Combined cycles, Heat storage, Hydrogen, Heat, Compressed air, High temperature, Combined cycle gas turbines, Carbon, Cycles, Energy storage

Proceedings Papers

100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

Charles Forsberg

Paper No: ICONE28-64632

DOI: https://doi.org/10.1115/ICONE28-64632

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Topics: Heat, Heat storage, Rocks, Stress, Storage, Fluids, Heat transfer, Plasma spraying, Spraying (Coating processes), Dimensions

Proceedings Papers

Solving the Challenges of Early Storage of Spent Fuel: the SENTRY™ Spent Fuel Management System

Timothy M. Lloyd

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, V003T11A014, August 4–6, 2021

Paper No: ICONE28-66590

DOI: https://doi.org/10.1115/ICONE28-66590

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Topics: Cooling, Radiation (Physics), Spent nuclear fuels, Storage

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

Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator

Ramon J. M. Pulido, Eric R. Lindgren, Samuel G. Durbin, Alex Salazar

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A031, August 4–5, 2020

Paper No: ICONE2020-16598

DOI: https://doi.org/10.1115/ICONE2020-16598

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Topics: Air flow, Cladding systems (Building), Cooling, Gases, Heat conduction, Model validation, Physics, Spent nuclear fuels, Storage, Temperature

Proceedings Papers

Analysis of Water Retention in Isothermal Vacuum Drying Test

Alex Salazar, III, Ramon J. M. Pulido, Eric R. Lindgren, Samuel G. Durbin

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A013, August 4–5, 2020

Paper No: ICONE2020-16599

DOI: https://doi.org/10.1115/ICONE2020-16599

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Topics: Drying, Storage, Vacuum, Water

Proceedings Papers

Evaluation of the Mixing Vanes Effect on the Hydrogen Diffusion and Hydride Formation in the Fuel Cladding

Ahmed Aly, Victor Petrov, Maria Avramova, Annalisa Manera, Kostadin Ivanov

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A087, July 22–26, 2018

Paper No: ICONE26-82431

DOI: https://doi.org/10.1115/ICONE26-82431

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Topics: Cladding systems (Building), Diffusion (Physics), Fuels, Hydrogen, Coolants, Fuel rods, Temperature gradient, Temperature profiles, Water, Boundary-value problems

2 3 4 5

NARROW

PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

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

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

Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister

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

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

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

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

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

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

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

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

Solving the Challenges of Early Storage of Spent Fuel: the SENTRY™ Spent Fuel Management System

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

Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator

Analysis of Water Retention in Isothermal Vacuum Drying Test

Evaluation of the Mixing Vanes Effect on the Hydrogen Diffusion and Hydride Formation in the Fuel Cladding

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