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Proceedings Papers

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Xifeng Lu, Furui Xiong, Xinjun Wang, Honglei Ai, Bingjin Li, Xuejiao Shao, Kang Yang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A017, August 8–12, 2022

Paper No: ICONE29-90677

DOI: https://doi.org/10.1115/ICONE29-90677

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Topics: Boilers, Dynamic response, Heat transfer, Time-domain analysis, Stress, Modal analysis, Dynamic response analysis, Emission spectroscopy, Finite element model, Frequency-domain analysis

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

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

Proceedings Papers

Static Application of Transient Hydrodynamic Loads on Vessel Internal Structures As a Result of Pulse Jet Mixer Overblow: High-Frequency Load Acoustic Event

Brian Fant, Rafael Garcilazo, Robert Blevins

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, V001T03A001, August 4–5, 2020

Paper No: ICONE2020-16047

DOI: https://doi.org/10.1115/ICONE2020-16047

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Topics: Acoustics, Modal analysis, Pulsejets, Spectra (Spectroscopy), Stress, Transients (Dynamics), Vessels

Proceedings Papers

Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator in Two Phase Flow

Huang Xuan, Qi Huan-huan, Cai Feng-chun, Feng Zhi-peng, Liu Shuai, Huang Qian

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A014, July 22–26, 2018

Paper No: ICONE26-81537

DOI: https://doi.org/10.1115/ICONE26-81537

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Topics: Boilers, Flow-induced vibrations, Heat transfer, Two-phase flow, Excitation, Fluids, Turbulence, Design, Displacement, Failure

Proceedings Papers

Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve

Jun Wu, Fan Bai, Yong Liu, Xingsheng Lao, Chunhui Dai

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A032, July 22–26, 2018

Paper No: ICONE26-82137

DOI: https://doi.org/10.1115/ICONE26-82137

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Topics: Power stations, Safety, Ships, Shock (Mechanics), Valves, Stress, Modal analysis, Stress concentration, ASME Standards, Emission spectroscopy

Proceedings Papers

Seismic Performance of PCS Water Storage Tank Considering Fluid-Structure Interaction

Hongliang Gou, ZiDuan Shang, Yugang Sun, Meng Chu, Honghui Ge

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A036, July 2–6, 2017

Paper No: ICONE25-66338

DOI: https://doi.org/10.1115/ICONE25-66338

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Topics: Fluid structure interaction, Water storage, Water, Sloshing, Design, Dynamic response, Finite element model, Modal analysis, Shear (Mechanics), Springs

Proceedings Papers

The Applicability Study on the Multi-Layer Shell Element Method in Steel Concrete Structure of Shield Building

Wei Chao

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A106, July 2–6, 2017

Paper No: ICONE25-67677

DOI: https://doi.org/10.1115/ICONE25-67677

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Topics: Concretes, Shells, Steel, Finite element analysis, Aircraft, Composite materials, Computer software, Design, Emission spectroscopy, Exterior walls

Proceedings Papers

Steam Generator Modal Analysis of Nuclear Power Plant

Lu Yan, Chu Qibao, Wang Qing, Fang Yonggang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A110, July 2–6, 2017

Paper No: ICONE25-67710

DOI: https://doi.org/10.1115/ICONE25-67710

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Topics: Boilers, Modal analysis, Nuclear power stations, Design, Nuclear reactor coolants

Proceedings Papers

Wet Modal Analysis of Wire-Wrapped Fuel Rod With the Axial Flow

Haidong Liu, Deqi Chen, Lian Hu

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A043, July 2–6, 2017

Paper No: ICONE25-67256

DOI: https://doi.org/10.1115/ICONE25-67256

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Topics: Axial flow, Fuel rods, Modal analysis, Wire, Fluids, Boundary-value problems, Computational fluid dynamics, Computer simulation, Engineering simulation, Finite element methods

Proceedings Papers

Simulation of Cross-Flow Vortex-Induced Vibration of Single Tube Based on Two-Way Fluid-Solid Interaction Method

Wang Zengzeng, Lu Tao, Liu Bo

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A031, July 2–6, 2017

Paper No: ICONE25-66955

DOI: https://doi.org/10.1115/ICONE25-66955

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Topics: Cross-flow, Fluids, Simulation, Vortex-induced vibration, Cylinders, Vibration, Vortex shedding, Displacement, Oscillating frequencies, Flow (Dynamics)

Proceedings Papers

Impact Resistant Design for FLEX Building Equipment Door

Shakir Y. Haider, David J. Calhoun

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A015, June 26–30, 2016

Paper No: ICONE24-60727

DOI: https://doi.org/10.1115/ICONE24-60727

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Topics: Design, Doors, Dynamic response, Earthquakes, Emergencies, Fukushima nuclear disaster, Japan, 2011, Missiles, Natural disasters, Nuclear power stations, Storage

Proceedings Papers

Seismic Response Spectrum Analysis on Advanced PWR Coolant System

Rong Duan, Lili Tong, Xuewu Cao

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A033, July 29–August 2, 2013

Paper No: ICONE21-15825

DOI: https://doi.org/10.1115/ICONE21-15825

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Topics: Coolants, Emission spectroscopy, Pressurized water reactors, Spectroscopy, Stress, Earthquakes, Boilers, Design, Pressure, Pumps

Proceedings Papers

Analysis of Liquid Sloshing in an In-Containment Refueling Water Storage Tank for AP1000

Yu Liu, Daogang Lu, Junjie Dang, Licun Wu, Wenhui Ma

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A034, July 29–August 2, 2013

Paper No: ICONE21-16007

DOI: https://doi.org/10.1115/ICONE21-16007

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Topics: Containment, Modal analysis, Sloshing, Water storage, Waves

Proceedings Papers

Dynamic Analysis of Elastic Structures on Spreadsheet

J.-M. Rambach

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 197-204, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55176

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55176

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Topics: Degrees of freedom, Design, Dynamic analysis, Finite element analysis, Modal analysis, Probabilistic safety assessment

Proceedings Papers

Modal Analysis for APR+ Reactor Barrel

Heung Seok Kang, Kang Hee Lee, Tae Soon Kwon

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 329-332, May 17–21, 2010

Paper No: ICONE18-30170

DOI: https://doi.org/10.1115/ICONE18-30170

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Topics: Damping, Ducts, Emergencies, Finite element analysis, Fluids, Modal analysis, Nuclear power, Safety, Stiffness, Vessels

Proceedings Papers

A Modal Analysis Procedure for PWR Fuel Assemblies

Le´o A. Carrilho, Jayme P. de Gouveˆa

Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 33-37, May 11–15, 2008

Paper No: ICONE16-48125

DOI: https://doi.org/10.1115/ICONE16-48125

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Topics: Fuels, Modal analysis, Pressurized water reactors, Stiffness, Structural analysis, Design, Finite element model, Fuel rods, Manufacturing, Nuclear fuels

Proceedings Papers

Evaluation of Seismic Integrity for an Integral Reactor Assembly

Soon Myeon Wang, J. S. Kim, T. E. Jin, M. J. Jhung, Y. H. Choi, J. C. Jo

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 361-365, April 25–29, 2004

Paper No: ICONE12-49512

DOI: https://doi.org/10.1115/ICONE12-49512

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Topics: Manufacturing, Modal analysis, Seismic analysis

NARROW

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

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

Static Application of Transient Hydrodynamic Loads on Vessel Internal Structures As a Result of Pulse Jet Mixer Overblow: High-Frequency Load Acoustic Event

Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator in Two Phase Flow

Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve

Seismic Performance of PCS Water Storage Tank Considering Fluid-Structure Interaction

The Applicability Study on the Multi-Layer Shell Element Method in Steel Concrete Structure of Shield Building

Steam Generator Modal Analysis of Nuclear Power Plant

Wet Modal Analysis of Wire-Wrapped Fuel Rod With the Axial Flow

Simulation of Cross-Flow Vortex-Induced Vibration of Single Tube Based on Two-Way Fluid-Solid Interaction Method

Impact Resistant Design for FLEX Building Equipment Door

Seismic Response Spectrum Analysis on Advanced PWR Coolant System

Analysis of Liquid Sloshing in an In-Containment Refueling Water Storage Tank for AP1000

Dynamic Analysis of Elastic Structures on Spreadsheet

Modal Analysis for APR+ Reactor Barrel

A Modal Analysis Procedure for PWR Fuel Assemblies

Evaluation of Seismic Integrity for an Integral Reactor Assembly

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