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Proceedings Papers

Effect of Pitch Ratio and Flat Bar Support Conditions on FEI Threshold for Low MDP Parallel Triangular Array – Single-Phase Water-Flow

Amro Elhelaly, Marwan Hassan, David Weaver, Soha Eid Moussa

Proc. ASME. PVP2022, Volume 3: Fluid-Structure Interaction; High Pressure Technology, V003T04A011, July 17–22, 2022

Paper No: PVP2022-86694

DOI: https://doi.org/10.1115/PVP2022-86694

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Topics: Flow (Dynamics), Water, Brass (Metal), Clearances (Engineering), Damping, Flow-induced vibrations, Instrumentation, Nuclear reactor steam generators, Rods, Stability

Proceedings Papers

Flow-Induced Vibration Simulations of a Straight Tube Bundle in Water Cross-Flow, Through URANS Approach

Daniele Vivaldi, Jean Baccou

Proc. ASME. PVP2022, Volume 3: Fluid-Structure Interaction; High Pressure Technology, V003T04A003, July 17–22, 2022

Paper No: PVP2022-81757

DOI: https://doi.org/10.1115/PVP2022-81757

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Topics: Cross-flow, Engineering simulation, Flow-induced vibrations, Simulation, Water, Fluids, Computer simulation, Vibration, Turbulence, Boilers

Proceedings Papers

Damage Detection Using Multiphysics Guided Wave Propagation

J. Dana, Y. H. Park, C. Gonzales

Proc. ASME. PVP2020, Volume 2: Computer Technology and Bolted Joints, V002T02A021, August 3, 2020

Paper No: PVP2020-21599

DOI: https://doi.org/10.1115/PVP2020-21599

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Topics: Damage, Wave propagation, Waves, Actuators, Signals, Simulation, Transients (Dynamics), Tubing, Aircraft, Computation

Proceedings Papers

Pitch and Pattern Effects on Streamwise Fluidelastic Instability in Tube Arrays

Marwan Hassan, David Weaver

Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A012, July 14–19, 2019

Paper No: PVP2019-93327

DOI: https://doi.org/10.1115/PVP2019-93327

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Topics: Damping, Failure, Flow (Dynamics), Flow-induced vibrations, Geometry, Modeling, Nuclear reactor steam generators, Power stations, Stability

Proceedings Papers

Effects of Initial Pressure and Length of a Broken Pipe on the Transient Hydraulic Loads Acting on Nuclear Steam Generator Tubes and Supports During Blowdown Following a Sudden Feedwater Pipe Break

Jong Chull Jo, Jae-Jun Jeong, Byong-Jo Yun

Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A033, July 14–19, 2019

Paper No: PVP2019-93132

DOI: https://doi.org/10.1115/PVP2019-93132

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Topics: Feedwater, Nuclear reactor steam generators, Pipes, Pressure, Stress, Transients (Dynamics), Pressurized water reactors, Boilers, Flow (Dynamics), Unsteady flow

Proceedings Papers

An Experimental Investigation of the Dynamics of a Loosely Supported Tube Array

Amro Elhelaly, Marwan Hassan, Atef Mohany, Soha Moussa

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A056, July 16–20, 2017

Paper No: PVP2017-65898

DOI: https://doi.org/10.1115/PVP2017-65898

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Topics: Dynamics (Mechanics), Clearances (Engineering), Cross-flow, Wear, Failure, Fatigue, Flow (Dynamics), Flow-induced vibrations, Friction, Manufacturing

Proceedings Papers

Investigations of In-Plane Fluidelastic Instability in a Multi-Span U-Bend Tube Bundle: Tests in Air Flow

Paul Feenstra, Teguewinde Sawadogo, Bruce Smith, Victor Janzen, Helen Cothron

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A062, July 16–20, 2017

Paper No: PVP2017-66068

DOI: https://doi.org/10.1115/PVP2017-66068

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Topics: Air flow, Cross-flow, Flow-induced vibrations, Boilers, Clearances (Engineering), Electricity (Physics), Nuclear reactor steam generators, Refrigerants, Steam, Two-phase flow

Proceedings Papers

Online Stress Corrosion Crack Monitoring in Nuclear Reactor Components Using Active Ultrasonic Sensor Networks and Nonlinear System Identification: Data Fusion Based Big Data Analytics Approach

Subhasish Mohanty, Bryan Jagielo, Chi Bum Bahn, Saurindranath Majumdar, Krishnamurti Natesan

Proc. ASME. PVP2015, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Competition and 23rd Annual Student Paper Competition; ASME NDE Division, V005T10A005, July 19–23, 2015

Paper No: PVP2015-45849

DOI: https://doi.org/10.1115/PVP2015-45849

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Topics: Data fusion, Nonlinear systems, Nuclear reactors, Stress corrosion cracking, Ultrasonic transducers, Inspection, Damage, Nondestructive evaluation, Sensors, Failure mechanisms

Proceedings Papers

Streamwise Dynamics of a Tube Array Subjected to Two-Phase Cross-Flows

Stephen Olala, Njuki W. Mureithi

Proc. ASME. PVP2015, Volume 4: Fluid-Structure Interaction, V004T04A044, July 19–23, 2015

Paper No: PVP2015-45714

DOI: https://doi.org/10.1115/PVP2015-45714

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Topics: Cross-flow, Dynamics (Mechanics), Failure, Excitation, Accidents, Delays, Leakage, Nuclear reactor steam generators, Radioactive substances, Water

Proceedings Papers

An Experimental Study of Steam Generator Tube Loading During Blowdown

Ouajih Hamouda, David S. Weaver, Jovica Riznic

Proc. ASME. PVP2015, Volume 4: Fluid-Structure Interaction, V004T04A024, July 19–23, 2015

Paper No: PVP2015-45250

DOI: https://doi.org/10.1115/PVP2015-45250

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Topics: Boilers, Flow (Dynamics), Transients (Dynamics), Containment, Design, Fluids, Nuclear reactor steam generators, Physics, Radioactive substances, Steam

Proceedings Papers

Instrumentation Development and Validation for an Experimental Study of Steam Generator Tube Loading During Blowdown

Ouajih Hamouda, David S. Weaver, Jovica Riznic

Proc. ASME. PVP2014, Volume 5: High-Pressure Technology; ASME NDE Division; 22nd Scavuzzo Student Paper Symposium and Competition, V005T11A004, July 20–24, 2014

Paper No: PVP2014-28137

DOI: https://doi.org/10.1115/PVP2014-28137

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Topics: Boilers, Instrumentation, Accidents, Steam, Boiling, Containment, Design, Flow visualization, Fluid measurement, Heat exchangers

Proceedings Papers

Crack Growth Prediction and Leakage Potential of Steam Generator Tubes Subjected to Flow Induced Vibrations

Salim El Bouzidi, Marwan Hassan, Jovica Riznic

Proc. ASME. PVP2014, Volume 4: Fluid-Structure Interaction, V004T04A045, July 20–24, 2014

Paper No: PVP2014-28442

DOI: https://doi.org/10.1115/PVP2014-28442

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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Leakage, Vibration, Nuclear reactor steam generators, Turbulence, Clearances (Engineering), Crack propagation, Engineering simulation

Proceedings Papers

Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break

Jong Chull Jo, Frederick J. Moody

Proc. ASME. PVP2014, Volume 4: Fluid-Structure Interaction, V004T04A095, July 20–24, 2014

Paper No: PVP2014-28134

DOI: https://doi.org/10.1115/PVP2014-28134

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Topics: Nuclear reactor steam generators, Steam, Transients (Dynamics), Boilers, Accidents, Coolants, Pipes, Stress, Computational fluid dynamics, Dimensions

Proceedings Papers

ASME Section III Stress Analysis of a Heat Exchanger Tubesheet With a Misdrilled Hole and Irregular or Thin Ligaments

Enrique Gomez, Roberto Ruiz, Robert M. (Con) Wilson

Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A100, July 14–18, 2013

Paper No: PVP2013-97075

DOI: https://doi.org/10.1115/PVP2013-97075

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Topics: Heat exchangers, Stress analysis (Engineering), Boilers, Flat plates, Nuclear reactor steam generators, Stress

Proceedings Papers

Commissioning Tests for an Experimental Study of Steam Generator Tube Loading During Blowdown

Ouajih Hamouda, David S. Weaver, Jovica Riznic

Proc. ASME. PVP2013, Volume 4: Fluid-Structure Interaction, V004T04A074, July 14–18, 2013

Paper No: PVP2013-97809

DOI: https://doi.org/10.1115/PVP2013-97809

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Topics: Boilers, Transients (Dynamics), Accidents, Radioactive substances, Boiling, Containment, Data collection, Design, Dynamics (Mechanics), Fluids

Proceedings Papers

Aging Management of French PWR Nuclear Steam Generators Using Statistical Modeling

Amit Chaudhary, Cédric Mathon, Nadine Gay

Proc. ASME. PVP2013, Volume 7: Operations, Applications and Components, V007T07A022, July 14–18, 2013

Paper No: PVP2013-97533

DOI: https://doi.org/10.1115/PVP2013-97533

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Topics: Modeling, Nuclear reactor steam generators, Pressurized water reactors, Boilers, Computational methods, Design, Heat, Manufacturing, Risk assessment, Safety

Proceedings Papers

Comparison of Design Requirements for Nuclear Steam Generators in the ASME and RCC-M Codes

Junjie Cao, Peter Caple

Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A061, July 14–18, 2013

Paper No: PVP2013-97438

DOI: https://doi.org/10.1115/PVP2013-97438

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Topics: Design, Nuclear reactor steam generators, Boilers, ASME Standards, Nuclear power stations, Pressure, ASME Boiler and Pressure Vessel Code

Proceedings Papers

Pressure Coefficient Distribution Over Tube Surfaces of Tube Bundle Subjected in Two-Phase Flow

W. G. Sim

Proc. ASME. PVP2011, Volume 4: Fluid-Structure Interaction, 227-233, July 17–21, 2011

Paper No: PVP2011-57296

DOI: https://doi.org/10.1115/PVP2011-57296

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Topics: Pressure, Two-phase flow, Vibration, Excitation, Flow-induced vibrations, Heat exchangers, Condensers (steam plant), Cross-flow, Failure, Fatigue

Proceedings Papers

A Numerical Characterization of Flow-Induced Vibration and Fretting Wear Potential in Nuclear Steam Generator Tube Bundles

Marwan Hassan, Atef Mohany

Proc. ASME. PVP2011, Volume 4: Fluid-Structure Interaction, 141-149, July 17–21, 2011

Paper No: PVP2011-57182

DOI: https://doi.org/10.1115/PVP2011-57182

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Topics: Flow-induced vibrations, Nuclear reactor steam generators, Wear, Failure, Dynamics (Mechanics), Damage, Clearances (Engineering), Plates (structures), Turbulence, Vibration

Proceedings Papers

Design Specifications to Ensure Flow-Induced Vibration and Fretting-Wear Performance in CANDU™ Steam Generators and Heat Exchangers

Victor Janzen, Yingke Han, Michel Pettigrew

Proc. ASME. PVP2009, Volume 4: Fluid-Structure Interaction, 507-516, July 26–30, 2009

Paper No: PVP2009-78078

DOI: https://doi.org/10.1115/PVP2009-78078

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Topics: Boilers, Design, Flow-induced vibrations, Heat exchangers, Wear, Excitation, Computer simulation, Nuclear reactor steam generators, Steam, Turbulence

NARROW

Effect of Pitch Ratio and Flat Bar Support Conditions on FEI Threshold for Low MDP Parallel Triangular Array – Single-Phase Water-Flow

Flow-Induced Vibration Simulations of a Straight Tube Bundle in Water Cross-Flow, Through URANS Approach

Damage Detection Using Multiphysics Guided Wave Propagation

Pitch and Pattern Effects on Streamwise Fluidelastic Instability in Tube Arrays

Effects of Initial Pressure and Length of a Broken Pipe on the Transient Hydraulic Loads Acting on Nuclear Steam Generator Tubes and Supports During Blowdown Following a Sudden Feedwater Pipe Break

An Experimental Investigation of the Dynamics of a Loosely Supported Tube Array

Investigations of In-Plane Fluidelastic Instability in a Multi-Span U-Bend Tube Bundle: Tests in Air Flow

Online Stress Corrosion Crack Monitoring in Nuclear Reactor Components Using Active Ultrasonic Sensor Networks and Nonlinear System Identification: Data Fusion Based Big Data Analytics Approach

Streamwise Dynamics of a Tube Array Subjected to Two-Phase Cross-Flows

An Experimental Study of Steam Generator Tube Loading During Blowdown

Instrumentation Development and Validation for an Experimental Study of Steam Generator Tube Loading During Blowdown

Crack Growth Prediction and Leakage Potential of Steam Generator Tubes Subjected to Flow Induced Vibrations

Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break

ASME Section III Stress Analysis of a Heat Exchanger Tubesheet With a Misdrilled Hole and Irregular or Thin Ligaments

Commissioning Tests for an Experimental Study of Steam Generator Tube Loading During Blowdown

Aging Management of French PWR Nuclear Steam Generators Using Statistical Modeling

Comparison of Design Requirements for Nuclear Steam Generators in the ASME and RCC-M Codes

Pressure Coefficient Distribution Over Tube Surfaces of Tube Bundle Subjected in Two-Phase Flow

A Numerical Characterization of Flow-Induced Vibration and Fretting Wear Potential in Nuclear Steam Generator Tube Bundles

Design Specifications to Ensure Flow-Induced Vibration and Fretting-Wear Performance in CANDU™ Steam Generators and Heat Exchangers

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