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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
https://doi.org/10.1115/ICONE29-91275
View Paper titled, Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium
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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

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
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

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
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

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
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

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
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Topics: Ships, Small modular reactors, Spent fuel storage, Storage, Accidents, Boron, Deformation, Fuel storage, Fuels, Accounting
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
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
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
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

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
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

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
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

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
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

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
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

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
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

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
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

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
https://doi.org/10.1115/ICONE28-64638
View Paper titled, Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power
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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
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, V001T02A027, August 4–6, 2021
Paper No: ICONE28-64632
https://doi.org/10.1115/ICONE28-64632
View Paper titled, 100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations
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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
https://doi.org/10.1115/ICONE28-66590
View Paper titled, Solving the Challenges of Early Storage of Spent Fuel: the SENTRY™ Spent Fuel Management System
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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
https://doi.org/10.1115/ICONE2020-16812
View Paper titled, Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation
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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
https://doi.org/10.1115/ICONE2020-16598
View Paper titled, Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator
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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
https://doi.org/10.1115/ICONE2020-16599
View Paper titled, Analysis of Water Retention in Isothermal Vacuum Drying Test
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Topics: Drying, Storage, Vacuum, Water
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
https://doi.org/10.1115/ICONE26-81621
View Paper titled, Finite Element Analysis for Fuel Assembly Structural Behavior
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Topics: Finite element analysis, Fuels, Manufacturing, Accidents, Computer software, Failure mechanisms, Finite element model, Mechanical behavior, Mechanical testing, Radioactive substances