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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, V003T08A006, August 4–6, 2021

Paper No: ICONE28-64436

DOI: https://doi.org/10.1115/ICONE28-64436

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Topics: Bubbles, Bubbly flow, Computational fluid dynamics, Simulation, Flow (Dynamics), Boilers, Boiling, Collisions (Physics), Fluids, Heat transfer

Proceedings Papers

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Hui Fu, Daogang Lu, Yu Liu

Paper No: ICONE28-64082

DOI: https://doi.org/10.1115/ICONE28-64082

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Topics: Alloys, Safety, Earthquakes, Collisions (Physics), Computer simulation, Coolants, Finite element methods, Leakage, Neutrons, Nuclear fuels

Proceedings Papers

Study on Seismic Isolation and Hi-Frequency Vibration Isolation Technology for Equipment in Nuclear Power Plant Using Aero Floating Technique

Kiyotaka Takito, Osamu Furuya, Hiroshi Kurabayashi, Kunio Sanpei

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A053, August 4–5, 2020

Paper No: ICONE2020-16940

DOI: https://doi.org/10.1115/ICONE2020-16940

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Topics: Earthquakes, Nuclear power stations, Vibration isolation, Vibration, Collisions (Physics), Countermeasures, Insulation, Levitation, Pressure

Proceedings Papers

Numerical Study of Collision Behavior of Melt Drops During Fuel-Coolant Interaction

Panpan Wen, Gen Li, Jinchen Gao, Yupeng Li, Akifumi Yamaji, Junjie Yan

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A013, August 4–5, 2020

Paper No: ICONE2020-16206

DOI: https://doi.org/10.1115/ICONE2020-16206

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Topics: Collisions (Physics), Computer simulation, Coolants, Drops, Fuels

Proceedings Papers

Interfacial Area Transport Model for Bubbly Flow System in Vertical Rod Bundle With Spacer Grids

Hang Liu, Jianyong Lai, Yi Li, Yulong Zhang, Minghao Liu, Liangming Pan

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A006, August 4–5, 2020

Paper No: ICONE2020-16108

DOI: https://doi.org/10.1115/ICONE2020-16108

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Topics: Bubbles, Bubbly flow, Collisions (Physics), Fuel rods

Proceedings Papers

CFD-DEM Simulations of Graphite Particle Collisions in Opposed Jet Mill

Sifan Peng, Yujia Liu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

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, V001T03A008, August 4–5, 2020

Paper No: ICONE2020-16340

DOI: https://doi.org/10.1115/ICONE2020-16340

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Topics: Computational fluid dynamics, Discrete element methods, Engineering simulation, Graphite, Particle collisions, Simulation, Particulate matter, Flow (Dynamics), Collisions (Physics), Air flow

Proceedings Papers

Enhancement of Pressure and Curvature Calculation for the Moving Particle Semi-Implicit Method

Jiazhi Li, Sunghyon Jang, Akira Yamaguchi

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A037, July 22–26, 2018

Paper No: ICONE26-82205

DOI: https://doi.org/10.1115/ICONE26-82205

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Topics: Particulate matter, Pressure, Collisions (Physics), Bubbles, Dams, Fluids, Gaussian distribution, Hydrostatic pressure, Oscillations, Pressure gradient

Proceedings Papers

Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density

Shogo Noda, Sukarman Sukarman, Akifumi Yamaji, Tetsuo Takei, Takanari Fukuda, Arisa Ayukawa

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A011, July 22–26, 2018

Paper No: ICONE26-81501

DOI: https://doi.org/10.1115/ICONE26-81501

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Topics: Coolants, Density, Design, Fuels, Breeder reactors, Collisions (Physics), Neutron flux, Neutrons, Probability, Temperature

Proceedings Papers

Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals

Guang-bo Cai, Ya-dong Zhang, Yu-xiang Han, Jia-pei Yu

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A041, July 22–26, 2018

Paper No: ICONE26-82132

DOI: https://doi.org/10.1115/ICONE26-82132

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Topics: Damage, Metals, Neutrons, Radiation (Physics), Simulation, Zirconium, Computer simulation, Alloys, Atoms, Spectra (Spectroscopy)

Proceedings Papers

A Piezoelectric Droplet Generating Device for Experiment in Successive Droplets Impacting Onto Solid Surface

Jianxin Li, Huang Zhang, Yuzheng Li, Qianfeng Liu, Hanliang Bo

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A045, July 22–26, 2018

Paper No: ICONE26-81475

DOI: https://doi.org/10.1115/ICONE26-81475

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Topics: Drops, Generators, Signals, Nozzles, US Department of Defense, Aluminum plate, Boilers, Collisions (Physics), Control systems, Design

Proceedings Papers

A Numerical Study on Graphite Dust Deposition on Steam Generator Tubes in the High-Temperature Gas-Cooled Reactor (HTGR)

Mingzhe Wei, Yiyang Zhang, Zhu Fang, Xinxin Wu, Libin Sun

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A024, July 22–26, 2018

Paper No: ICONE26-82043

DOI: https://doi.org/10.1115/ICONE26-82043

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Topics: Boilers, Dust, Graphite, Very high temperature reactors, Particulate matter, Adhesion, Finite element methods, Simulation, Accidents, Collisions (Physics)

Proceedings Papers

A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM

Song Yu, Zhou Qin, Zhao Jiaqing, Zhang Yiyang, Wu Xinxin

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A018, July 22–26, 2018

Paper No: ICONE26-81229

DOI: https://doi.org/10.1115/ICONE26-81229

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Topics: Boilers, Flow-induced vibrations, Pipes, Cylinders, Vibration, High temperature, ASME Standards, Circular cylinders, Collisions (Physics), Damage

Proceedings Papers

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

Jinhua Wang, Bing Wang, Bin Wu, Yue Li, Haitao Wang

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A001, July 22–26, 2018

Paper No: ICONE26-81022

DOI: https://doi.org/10.1115/ICONE26-81022

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Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines

Proceedings Papers

Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method

Dida Zhang, Guobin Jia, Long He, Jiajie Shen, Zhichao Zhan, Hailing Wang, Wei Guo

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A045, July 2–6, 2017

Paper No: ICONE25-67194

DOI: https://doi.org/10.1115/ICONE25-67194

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Topics: Collisions (Physics), High temperature, Probability, Fuels, Generation IV reactors, Neutron flux

Proceedings Papers

Numerical Simulation of Graphite Dust Deposition in Pebble Bed Reactor Core of HTGR

Tao Chen, Jie Wang, Wei Peng, Xiaokai Sun

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A071, July 2–6, 2017

Paper No: ICONE25-67052

DOI: https://doi.org/10.1115/ICONE25-67052

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Topics: Computer simulation, Dust, Graphite, Very high temperature reactors, Particulate matter, Temperature, Collisions (Physics), Fuels, Simulation, Flow (Dynamics)

Proceedings Papers

Study on Water Hammer in the Overpressure Discharge Pipe of Nuclear Power Plant

Qingmu Xu, Kun Cai, Jie Qin, Junkai Yuan, Juan Li

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A031, July 2–6, 2017

Paper No: ICONE25-66459

DOI: https://doi.org/10.1115/ICONE25-66459

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Topics: Nuclear power stations, Pipes, Water hammer, Steam, Pressure, Spent nuclear fuels, Valves, Water, Cavities, Collisions (Physics)

Proceedings Papers

Influence of Working Pressure and Pressure Difference on Static Droplet Evaporation Characteristics

Fulong Zhao, Chenru Zhao, Hanliang Bo, Ying Liu

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A004, July 2–6, 2017

Paper No: ICONE25-66039

DOI: https://doi.org/10.1115/ICONE25-66039

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Topics: Drops, Evaporation, Pressure, Steam, Water, Vapors, Nuclear power stations, Power stations, Separation (Technology), Water vapor

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

Experimental Study of Droplets Collision and Bag Breaking in Rotating Gas Flow Field

Experimental Study on Aerosol Penetration Through Concrete Cracks Under Inertial Collision and Steam Condensation

Assessment and Analysis of Various Mechanisms in the Coalescence and Breakup Models for Upward Bubbly Flow

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Study on Seismic Isolation and Hi-Frequency Vibration Isolation Technology for Equipment in Nuclear Power Plant Using Aero Floating Technique

Numerical Study of Collision Behavior of Melt Drops During Fuel-Coolant Interaction

Interfacial Area Transport Model for Bubbly Flow System in Vertical Rod Bundle With Spacer Grids

CFD-DEM Simulations of Graphite Particle Collisions in Opposed Jet Mill

Enhancement of Pressure and Curvature Calculation for the Moving Particle Semi-Implicit Method

Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density

Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals

A Piezoelectric Droplet Generating Device for Experiment in Successive Droplets Impacting Onto Solid Surface

A Numerical Study on Graphite Dust Deposition on Steam Generator Tubes in the High-Temperature Gas-Cooled Reactor (HTGR)

A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method

Numerical Simulation of Graphite Dust Deposition in Pebble Bed Reactor Core of HTGR

Study on Water Hammer in the Overpressure Discharge Pipe of Nuclear Power Plant

Influence of Working Pressure and Pressure Difference on Static Droplet Evaporation Characteristics

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