Search Results | ASME Digital Collection

1-20 of 36

Sort by

Sort Order Select

Proceedings Papers

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Donghao Li, Daogang Lu, Yuxuan Zhu, Yu Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A032, August 8–12, 2022

Paper No: ICONE29-92137

DOI: https://doi.org/10.1115/ICONE29-92137

View Paper

Topics: Fluid structure interaction, Pipes, Shells, Vibration, Finite element model, Fluids, Water, Computer software, Fast neutron reactors, Heat shielding

Proceedings Papers

Numerical Study of the Effect of Different Tank Shapes on Liquid Sloshing Characteristics

Yuxuan Zhu, Daogang Lu, Donghao Li, Yu Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A034, August 8–12, 2022

Paper No: ICONE29-92150

DOI: https://doi.org/10.1115/ICONE29-92150

View Paper

Topics: Fluid structure interaction, Shapes, Sloshing, Water

Proceedings Papers

Frequency Analysis of Liquid Metal Reactor Fuel Assemblies

Hui Fu, Daogang Lu, Yu Liu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A039, August 8–12, 2022

Paper No: ICONE29-93236

DOI: https://doi.org/10.1115/ICONE29-93236

View Paper

Topics: Fuels, Liquid metals, Manufacturing, Nuclear fuels

Proceedings Papers

Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor

Jun Zhang, Daogang Lu, Jinsong Guo, Yuhao Zhang, Danting Sui

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A025, August 8–12, 2022

Paper No: ICONE29-92794

DOI: https://doi.org/10.1115/ICONE29-92794

View Paper

Topics: Fast neutron reactors, Heat, Heat transfer, Sodium

Proceedings Papers

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Chaofan Zhang, Daogang Lu, Yu Liu, Haotian Qiu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A036, August 8–12, 2022

Paper No: ICONE29-92274

DOI: https://doi.org/10.1115/ICONE29-92274

View Paper

Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)

Proceedings Papers

CFD transient simulation of natural convection characteristics based on detailed core rod bundles model in PLANDTL-DHX experimental device

Xueyuan Zhang, Yuhao Zhang, Jingsong Guo, Daogang Lu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A037, August 8–12, 2022

Paper No: ICONE29-93169

DOI: https://doi.org/10.1115/ICONE29-93169

View Paper

Topics: Computational fluid dynamics, Computer simulation, Fuel rods, Natural convection, Simulation, Sodium fast reactors, Transients (Dynamics)

Proceedings Papers

Parameter Calculation Method of Porous Media Based on BP Neural Network

Fei Zhao, Daogang Lu, Yu Liu, Dong Liu, Jiliang Xu, Jinghui Wu, Fei Xie, Yuchao Wang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A089, August 8–12, 2022

Paper No: ICONE29-92382

DOI: https://doi.org/10.1115/ICONE29-92382

View Paper

Topics: Artificial neural networks, Computational methods, Fluid structure interaction, Porous materials

Proceedings Papers

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Yuchao Wang, Daogang Lu, Fei Zhao, Yu Liu

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A071, August 8–12, 2022

Paper No: ICONE29-92039

DOI: https://doi.org/10.1115/ICONE29-92039

View Paper

Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels

Proceedings Papers

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Jinsong Guo, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, Yuhao Zhang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A003, August 8–12, 2022

Paper No: ICONE29-92364

DOI: https://doi.org/10.1115/ICONE29-92364

View Paper

Topics: Computer simulation, Heat, Modeling, Flow (Dynamics), Wire, Fuel rods, Porous materials, Safety, Sodium fast reactors, Dynamics (Mechanics)

Proceedings Papers

The BDB-NS Hydrodynamic Model for Porous Spent Fuel Storage Racks Solved by Fourier Spectral Method

Yu Liu, Yuxuan Zhu, Fei Zhao, Dong Liu, Daogang Lu

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A023, August 8–12, 2022

Paper No: ICONE29-91760

DOI: https://doi.org/10.1115/ICONE29-91760

View Paper

Topics: Earthquakes, Spent fuel storage

Proceedings Papers

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Xinyue Luo, Daogang Lu, Jiaqi Feng, Yuhao Zhang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A040, August 8–12, 2022

Paper No: ICONE29-92323

DOI: https://doi.org/10.1115/ICONE29-92323

View Paper

Topics: Heat transfer, Radiation (Physics), Sodium fast reactors, Cavities, Fast neutron reactors, Temperature, Vessels, Computational fluid dynamics, Construction, Containers

Proceedings Papers

Numerical Research on Coupling Heat Transfer Characteristics of PRHR HX Primary and Secondary Sides

Jingwen Liu, Yuhao Zhang, Jingpin Fu, Daogang Lu

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A043, August 8–12, 2022

Paper No: ICONE29-92539

DOI: https://doi.org/10.1115/ICONE29-92539

View Paper

Topics: Computer simulation, Heat transfer

Proceedings Papers

Numerical Simulation of Added Mass in Narrow Gaps of Multi-Layer Thin-Walled Shell of Fast Reactor

Dexuan Duan, Daogang Lu, Yu Liu, Donghao Li

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, V003T08A009, August 4–6, 2021

Paper No: ICONE28-64644

DOI: https://doi.org/10.1115/ICONE28-64644

View Paper

Topics: Computer simulation, Fast neutron reactors, Finite element analysis, Fluid structure interaction, Shells

Proceedings Papers

Three-Dimensional Numerical Simulation on Transient Natural Circulation Characteristics of DRACS in PLANDTL-DHX Experimental Device

Zijia Chen, Daogang Lu, Jinsong Guo, Yuhao Zhang

Paper No: ICONE28-64515

DOI: https://doi.org/10.1115/ICONE28-64515

View Paper

Topics: Computer simulation, Sodium fast reactors, Transients (Dynamics)

Proceedings Papers

Yuhao Zhang, Daogang Lu, Bin Ouyang, Yonglong Yuan

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A064, July 22–26, 2018

Paper No: ICONE26-82518

DOI: https://doi.org/10.1115/ICONE26-82518

View Paper

Topics: Condensation, Heat transfer, Plasma spraying, Spraying (Coating processes), Steam, Flow (Dynamics), High pressure (Physics), High temperature, Oscillations, Pressurized water reactors

Journal citation

NARROW

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Numerical Study of the Effect of Different Tank Shapes on Liquid Sloshing Characteristics

Frequency Analysis of Liquid Metal Reactor Fuel Assemblies

Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

CFD transient simulation of natural convection characteristics based on detailed core rod bundles model in PLANDTL-DHX experimental device

Parameter Calculation Method of Porous Media Based on BP Neural Network

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

The BDB-NS Hydrodynamic Model for Porous Spent Fuel Storage Racks Solved by Fourier Spectral Method

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Numerical Research on Coupling Heat Transfer Characteristics of PRHR HX Primary and Secondary Sides

Numerical Simulation of Added Mass in Narrow Gaps of Multi-Layer Thin-Walled Shell of Fast Reactor

Three-Dimensional Numerical Simulation on Transient Natural Circulation Characteristics of DRACS in PLANDTL-DHX Experimental Device

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

Experimental and Numerical Research on Steam Direct Contact Condensation Process in Automatic Depressurization System of AP1000

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions

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

Experimental Comparison on the Multi-Hole Steam Spraying Condensation Heat Transfer Characteristics

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only