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Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

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, V001T04A014, August 4–6, 2021

Paper No: ICONE28-65689

DOI: https://doi.org/10.1115/ICONE28-65689

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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China

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

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Jin Feng Huang

Paper No: ICONE28-63314

DOI: https://doi.org/10.1115/ICONE28-63314

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Topics: Ceramics, Fuels, Pressurized water reactors, Cladding systems (Building), Cycles, Nuclear power stations, Silicon, Temperature, Thermal conductivity, Boron

Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux

Proceedings Papers

Migration Characteristics of Sub-Source Items in Breach Occurrences

Xu Peng, Tian Ruifeng

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, V003T08A008, August 4–6, 2021

Paper No: ICONE28-64606

DOI: https://doi.org/10.1115/ICONE28-64606

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Topics: Accidents, Aerosols, Computational fluid dynamics, Computer software, Coolants, Drag (Fluid dynamics), Flow (Dynamics), Fluids, Gravity (Force), Hazards

Proceedings Papers

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Yugao Ma, Minyun Liu, Wenbin Han, Biheng Xie, Xiaoming Chai, Shanfang Huang, Hongxing Yu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A006, August 4–5, 2020

Paper No: ICONE2020-16100

DOI: https://doi.org/10.1115/ICONE2020-16100

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Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors

Proceedings Papers

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Simona Breidokaitė, Andrius Tidikas, Gediminas Stankūnas

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A031, August 4–5, 2020

Paper No: ICONE2020-16465

DOI: https://doi.org/10.1115/ICONE2020-16465

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Topics: Vacuum, Vessels, Cooling, Shells, Water, Isotopes, Neutrons, Radioisotopes, Stainless steel, Design

Proceedings Papers

Experimental Study on Flow Patterns of Decaying Swirling Gas-Liquid Flow in a Horizontal Pipe

Shuai Liu, Li Liu, Jiarong Zhang, Hanyang Gu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A016, August 4–5, 2020

Paper No: ICONE2020-16224

DOI: https://doi.org/10.1115/ICONE2020-16224

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Topics: Flow (Dynamics), Pipes, Swirling flow, Separation (Technology), Water, Bubbles, Chain, Design, Drops, Fluids

Proceedings Papers

Experimental Study on Aerosol Collection by Spray Droplets: Application to Fission Products Removal in Containment

Haomin Sun, Yohan Leblois, Thomas Gelain, Emmanuel Porcheron

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A050, August 4–5, 2020

Paper No: ICONE2020-16857

DOI: https://doi.org/10.1115/ICONE2020-16857

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Topics: Aerosols, Computational fluid dynamics, Containment, Drops, Nuclear fission, Particulate matter, Sprays

Proceedings Papers

Numerical Simulation of Multi-Physics Processes in Nuclear System Based on Galerkin Finite Element Method

Baoxin Yuan, Wankui Yang, Songbao Zhang, Bin Zhong, Junxia Wei, Yangjun Ying

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, V001T02A005, August 4–5, 2020

Paper No: ICONE2020-16801

DOI: https://doi.org/10.1115/ICONE2020-16801

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Topics: Computer simulation, Finite element methods, Physics, Heat, Heat transfer, Temperature, Thermoelasticity, Finite element analysis, Neutron flux, Neutrons

Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song

Paper No: ICONE2020-16633

DOI: https://doi.org/10.1115/ICONE2020-16633

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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids

Proceedings Papers

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Changbing Tang, Yongjun Jiao, Yuanming Li, Yi Zhou, Kun Zhang

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A036, August 4–5, 2020

Paper No: ICONE2020-16387

DOI: https://doi.org/10.1115/ICONE2020-16387

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Topics: Cladding systems (Building), Computer simulation, Computer software, Fuel rods, Fuels, Stress, Failure, Pressure, Simulation, Transients (Dynamics)

Proceedings Papers

Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

Hironobu Iwanami, Tomoharu Hashimoto, Motoi Tanaka, Ryuichi Tayama, Satoshi Mizuno, Takashi Uemura

Paper No: ICONE2020-16721

DOI: https://doi.org/10.1115/ICONE2020-16721

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Topics: Boiling water reactors, Accidents, Evaluation methods, Pipes, Nuclear fission, Water, Coolants, Design, Evacuations, Pressure

Proceedings Papers

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

Rodney Harvill, Jeff Lane, John Link, Anita Gates, Tom Kindred

Paper No: ICONE2020-16058

DOI: https://doi.org/10.1115/ICONE2020-16058

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Topics: Design, Modeling, Molten salt reactors, Heat, Fuels, Neutrons, Transients (Dynamics), Flow (Dynamics), Fluids, Nuclear fission

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

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Muhammad Altahhan, Noah McFerran, Jonathan Morrell, Maria Avramova

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A031, July 22–26, 2018

Paper No: ICONE26-81464

DOI: https://doi.org/10.1115/ICONE26-81464

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Topics: Ceramic matrix composites, Cladding systems (Building), Silicon, Fuels, Pressurized water reactors, Critical heat flux, Design, Manufacturing, Pressure, Boiling

Proceedings Papers

Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT

Xiaohan Zhao, Mingjun Wang, Wenxi Tian, G. H. Su, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A042, July 22–26, 2018

Paper No: ICONE26-81641

DOI: https://doi.org/10.1115/ICONE26-81641

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Topics: Accidents, Boilers, Computer software, Coolants, Failure, Flow (Dynamics), Heat exchangers, Heat transfer, Maintenance, Nuclear fission

Proceedings Papers

Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA

Yanan He, Yingwei Wu, Shihuai Wang, Bowen Qiu, G. H. Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A070, July 22–26, 2018

Paper No: ICONE26-82076

DOI: https://doi.org/10.1115/ICONE26-82076

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Topics: Fuels, Composite materials, Light water reactors, Accidents, Nuclear fission, Thermal conductivity, Thermal properties, Cladding systems (Building), Coolants, Enthalpy

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

Multiphysics Modeling of Fabrication Methods’ Effect on UO 2 -BeO Composite Fuels’ Performance

Wei Zhou, Wenzhong Zhou

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A026, July 22–26, 2018

Paper No: ICONE26-81429

DOI: https://doi.org/10.1115/ICONE26-81429

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Topics: Composite materials, Fuels, Manufacturing, Modeling, Particulate matter, Thermal conductivity, Grain size, Accidents, Microcracks, Nuclear fission

2 3 4 5

NARROW

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

A Sodium-Cooled Thermal-Spectrum Fission Battery

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Migration Characteristics of Sub-Source Items in Breach Occurrences

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Experimental Study on Flow Patterns of Decaying Swirling Gas-Liquid Flow in a Horizontal Pipe

Experimental Study on Aerosol Collection by Spray Droplets: Application to Fission Products Removal in Containment

Numerical Simulation of Multi-Physics Processes in Nuclear System Based on Galerkin Finite Element Method

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

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

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT

Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA

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

Multiphysics Modeling of Fabrication Methods’ Effect on UO 2 -BeO Composite Fuels’ Performance

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