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Proceedings Papers

Automated Eddy Current Array Sensor Delivery Tool for Nondestructive Examination of Spent Fuel Pool Liner

Michael Smith, Emily Abbate, Joey Phillips, Byungsik Yoon

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, V001T01A007, August 4–6, 2021

Paper No: ICONE28-65628

DOI: https://doi.org/10.1115/ICONE28-65628

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Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Inspection, Nondestructive evaluation, Sensors, Spent nuclear fuels

Proceedings Papers

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang

Paper No: ICONE28-65406

DOI: https://doi.org/10.1115/ICONE28-65406

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Topics: Ceramics, Fast neutron reactors, High temperature, Neutrons, Nuclear fuel cycle, Physics, Spent nuclear fuels

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

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

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

Preliminary Development on Thermal-Hydraulic Analysis Code for the Spent Fuel Rod Under the Condition of Spray Cooling

Guo Chao, Deng Jian, Cai Rong, Ma Yugao, Liu Lili, Zhang Yuhao, Lv Siyu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A047, August 4–5, 2020

Paper No: ICONE2020-16798

DOI: https://doi.org/10.1115/ICONE2020-16798

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Topics: Cooling, Spent nuclear fuels, Sprays, Temperature, Blanks, Cladding systems (Building), Cooling systems, Evaporation, Failure, Film thickness

Proceedings Papers

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Yong Mann Song, Jong Yeob Jung, Sunil Nijhawan

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, V001T01A015, August 4–5, 2020

Paper No: ICONE2020-16634

DOI: https://doi.org/10.1115/ICONE2020-16634

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Topics: Accidents, Computer software, Spent nuclear fuels, Fuels, Fluids, Heavy water reactors, Radiation (Physics), Stainless steel, Steel, Water

Proceedings Papers

Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants

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

Paper No: ICONE2020-16157

DOI: https://doi.org/10.1115/ICONE2020-16157

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Topics: Cushioning materials, Design, Nuclear power stations, Spent nuclear fuels

Proceedings Papers

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Kenneth C. Wagner, David L. Y. Louie

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A045, August 4–5, 2020

Paper No: ICONE2020-16584

DOI: https://doi.org/10.1115/ICONE2020-16584

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Topics: Accidents, Fire, Explosions, Radioisotopes, Aerosols, Model development, Nuclear power stations, Probabilistic risk assessment, Safety, Spent nuclear fuels

Proceedings Papers

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Jeff Ridgway, Bryant Slater

Paper No: ICONE2020-16810

DOI: https://doi.org/10.1115/ICONE2020-16810

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Topics: Fluids, Gravity (Force), Sensors, Vessels, Leakage, Nuclear power, Sensor placement, Simulation, Accuracy and precision, Algorithms

Proceedings Papers

Neutronic Study on Conceptual Lithium Fluoride Salt Cooled Fusion Driven System for Actinide Transmutation

Feryantama Putra

Paper No: ICONE2020-16368

DOI: https://doi.org/10.1115/ICONE2020-16368

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Topics: Lithium, Coolants, Design, Fuel rods, Neutron sources, Chain, Combustion, Cycles, Fast neutron reactors, Fuels

Proceedings Papers

Experimental Setup for Non-Contact Displacement Measurement of Nuclear Waste via Electromagnetic Waves

Mauro Cappelli, Vincenzo Surrenti

Paper No: ICONE2020-16653

DOI: https://doi.org/10.1115/ICONE2020-16653

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Topics: Cables, Displacement measurement, Electromagnetic radiation, Radioactive wastes, Sensors, Computer simulation, Design, Electromagnetic fields, Energy consumption, Engineering prototypes

Proceedings Papers

Optimization of Fuel Storage in Spent Fuel Pool

Xinyu Wang, Richard Cable Kurwitz, Zhijian Zhang

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A006, July 22–26, 2018

Paper No: ICONE26-81084

DOI: https://doi.org/10.1115/ICONE26-81084

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Topics: Fuel storage, Optimization, Spent nuclear fuels, Algorithms, Manufacturing, Fuels, Genetic algorithms, Nuclear power stations, Vacuum

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

Proceedings Papers

Influence of Gap Size on Added Mass for Spent Fuel Storage Rack

Daogang Lu, Yu Liu, Shu Zheng

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A033, July 22–26, 2018

Paper No: ICONE26-82595

DOI: https://doi.org/10.1115/ICONE26-82595

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Topics: Spent fuel storage, Water, Spent nuclear fuels, Construction, Earthquakes, Fluid structure interaction, Fluids, Oscillating frequencies, Computational fluid dynamics, Design

Proceedings Papers

Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling

Hidemasa Yamano, Kenichi Naruto, Kenichi Kurisaka, Hiroyuki Nishino, Yasushi Okano

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A002, July 22–26, 2018

Paper No: ICONE26-81079

DOI: https://doi.org/10.1115/ICONE26-81079

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Topics: Sodium fast reactors, Storage tanks, Vessels, Failure, Accidents, Sodium, Fuels, Damage, Dampers, Design

Proceedings Papers

Assessment of Radiological Source Term Releases for Potential Severe Accident Scenarios in a PWR SFP

Kwang-Il Ahn, Jae-Uk Shin

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A004, July 22–26, 2018

Paper No: ICONE26-81633

DOI: https://doi.org/10.1115/ICONE26-81633

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Topics: Accidents, Pressurized water reactors, Cooling, Emergencies, Fukushima nuclear disaster, Japan, 2011, Nuclear fission, Spent nuclear fuels, Underground injection

Proceedings Papers

The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility

Liming Huang, Shouhai Yang, Jie Liu

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A011, July 22–26, 2018

Paper No: ICONE26-81552

DOI: https://doi.org/10.1115/ICONE26-81552

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Topics: Design, Pressurized water reactors, Radiation (Physics), Spent nuclear fuels, Storage, Safety, Spent fuel storage, China, Construction, Monte Carlo methods

2 3 4 5

NARROW

Automated Eddy Current Array Sensor Delivery Tool for Nondestructive Examination of Spent Fuel Pool Liner

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

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

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

Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator

Preliminary Development on Thermal-Hydraulic Analysis Code for the Spent Fuel Rod Under the Condition of Spray Cooling

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Neutronic Study on Conceptual Lithium Fluoride Salt Cooled Fusion Driven System for Actinide Transmutation

Experimental Setup for Non-Contact Displacement Measurement of Nuclear Waste via Electromagnetic Waves

Optimization of Fuel Storage in Spent Fuel Pool

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

Influence of Gap Size on Added Mass for Spent Fuel Storage Rack

Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling

Assessment of Radiological Source Term Releases for Potential Severe Accident Scenarios in a PWR SFP

The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility

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