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Proceedings Papers

Experimental Characterization of the Nonlinear Boundary Conditions Applied by Two Different Designs of Spacer Grids on PWR Fuel Rods

Giovanni Ferrari, Brian Painter, Giulio Franchini, Kostas Karazis, Marco Amabili

Proc. ASME. IMECE2022, Volume 5: Dynamics, Vibration, and Control, V005T07A099, October 30–November 3, 2022

Paper No: IMECE2022-96787

DOI: https://doi.org/10.1115/IMECE2022-96787

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Topics: Boundary-value problems, Experimental characterization, Fuel rods, Pressurized water reactors, Vibration, Springs, Coolants, Damping, Displacement, Excitation

Proceedings Papers

Evaluation of Fuel Rod Response Using Principal Component Analysis

Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis

Proc. ASME. IMECE2022, Volume 5: Dynamics, Vibration, and Control, V005T07A043, October 30–November 3, 2022

Paper No: IMECE2022-96808

DOI: https://doi.org/10.1115/IMECE2022-96808

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Topics: Cross-flow, Fuel rods, Pressurized water reactors, Principal component analysis, Vibration

Proceedings Papers

An Inverse Method for the Identification of a Distributed Random Excitation Acting on a Vibrating Structure: Part 2 — Flow-Induced Vibration Application

L. Perotin, S. Granger

Proc. ASME. IMECE97, 4th International Symposium on Fluid-Structure Interactions, Aeroelasticity, Flow-Induced Vibration and Noise: Volume I, 333-340, November 16–21, 1997

Paper No: IMECE1997-0075

DOI: https://doi.org/10.1115/IMECE1997-0075

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Topics: Flow-induced vibrations, Random excitation, Excitation, Turbulence, Computer software, Dynamic systems, Flow (Dynamics), Pressurized water reactors, Water, Wear

Proceedings Papers

Experimental and Computational Investigation Into Vibration Wear of Control Rods in French PWRs

Laurent Borsoi, Christian Canteneur, Gérard Barbe

Proc. ASME. IMECE97, 4th International Symposium on Fluid-Structure Interactions, Aeroelasticity, Flow-Induced Vibration and Noise: Volume II, 249-256, November 16–21, 1997

Paper No: IMECE1997-0118

DOI: https://doi.org/10.1115/IMECE1997-0118

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Topics: Pressurized water reactors, Rods, Vibration, Wear, Computation, Flow (Dynamics), Computer simulation, Displacement, Elevations (Drawings), Excitation

Proceedings Papers

Flow-Induced Vibration of a Tube Array in the Inlet Region of a High Performance Steam Generator: Part 1 — Turbulence Induced Vibration

Toshihiko Iwase, Takeshi Sunami, Kazuhiko Matsutani, Tomomichi Nakamura, Njuki W. Mureithi, Ayao Tsuge, Yoshinori Watanabe, Ken-ichi Tomomatsu, Osamu Takaba

Proc. ASME. IMECE97, 4th International Symposium on Fluid-Structure Interactions, Aeroelasticity, Flow-Induced Vibration and Noise: Volume II, 301-308, November 16–21, 1997

Paper No: IMECE1997-0124

DOI: https://doi.org/10.1115/IMECE1997-0124

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Topics: Boilers, Flow-induced vibrations, Turbulence, Vibration, Design, Nuclear power stations, Pressurized water reactors, Random vibration, Stability, Stress

Proceedings Papers

Prediction of Tube Wear due to Flow-Induced Vibration in PWR Steam Generators

M. S. M. Rao, L. J. Laskowski, G. S. Srikantiah, K. S. Ahluwalia

Proc. ASME. IMECE97, 4th International Symposium on Fluid-Structure Interactions, Aeroelasticity, Flow-Induced Vibration and Noise: Volume II, 257-264, November 16–21, 1997

Paper No: IMECE1997-0119

DOI: https://doi.org/10.1115/IMECE1997-0119

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Topics: Boilers, Flow-induced vibrations, Pressurized water reactors, Wear, Excitation, Finite element analysis, Flow (Dynamics), In-service inspection, Inspection, Maintenance

Proceedings Papers

CFD Analysis of Thermal Mixing and Stratification in AP600 Auxiliary Lines

Alexander W. Harkness, Richard E. Schwirian, Petr Dymacek

Proc. ASME. IMECE97, Nuclear Engineering, 115-122, November 16–21, 1997

Paper No: IMECE1997-0614

DOI: https://doi.org/10.1115/IMECE1997-0614

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Topics: Computational fluid dynamics, Piping systems, Pressurized water reactors, Thermal stratification

Proceedings Papers

Application of the W COBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis

Jinzhao Zhang, S. M. Bajorek, R. M. Kemper, M. E. Nissley, N. Petkov, L. E. Hochreiter

Proc. ASME. IMECE97, Nuclear Engineering, 15-33, November 16–21, 1997

Paper No: IMECE1997-0603

DOI: https://doi.org/10.1115/IMECE1997-0603

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Topics: Accidents, Approximation, Boundary-value problems, Cladding systems (Building), Coolants, Cooling, Design, Emergency core cooling systems, Film boiling, Heat transfer

Proceedings Papers

Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head

R. E. Schwirian

Proc. ASME. IMECE97, Nuclear Engineering, 65-70, November 16–21, 1997

Paper No: IMECE1997-0608

DOI: https://doi.org/10.1115/IMECE1997-0608

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Topics: Buoyancy, Computational fluid dynamics, Coolants, Pressurized water reactors, Stress, Temperature profiles, Transients (Dynamics)

Proceedings Papers

An Efficient Finite Element Method for the Representation of Fluid Structure Interaction in Large Structural Transient Dynamic Analyses

Alexander W. Harkness, Richard E. Schwirian

Proc. ASME. IMECE98, Fluids Engineering, 145-152, November 15–20, 1998

Paper No: IMECE1998-0997

DOI: https://doi.org/10.1115/IMECE1998-0997

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Topics: Dynamic analysis, Finite element methods, Fluid structure interaction, Transients (Dynamics), Fluids, Finite element analysis, Nuclear reactor coolants, Pressure, Accidents, Constraint equations

Proceedings Papers

CFD Analysis of a Direct Vessel Injection (DVI) Transient to Calculate AP600 Reactor Vessel Shell Temperatures

John C. Matarazzo, Richard E. Schwirian

Proc. ASME. IMECE98, Nuclear Engineering, 1-7, November 15–20, 1998

Paper No: IMECE1998-1127

DOI: https://doi.org/10.1115/IMECE1998-1127

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Topics: Computational fluid dynamics, Reactor vessels, Shells, Temperature, Transients (Dynamics), Vessels, Pressurized water reactors, Temperature distribution

Proceedings Papers

Uncertainty Quantification of SB LOCA With CSAU Using Optimal Statistical Estimator

Andrej Prošek, Borut Mavko

Proc. ASME. IMECE98, Nuclear Engineering, 15-21, November 15–20, 1998

Paper No: IMECE1998-1129

DOI: https://doi.org/10.1115/IMECE1998-1129

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Topics: Uncertainty quantification, Uncertainty, Accidents, Coolants, Safety, Algorithms, Cladding systems (Building), Computers, Pressurized water reactors, Response surface methodology

Proceedings Papers

A Review of SQL vs NoSQL Database for Nuclear Reactor Digital Twin Applications: With Example MongoDB Based NoSQL Database for Digital Twin Model of a Pressurized-Water-Reactor Steam-Generator

Subhasish Mohanty, Thomas W. Elmer, Sasan Bakhtiari, Richard B. Vilim

Proc. ASME. IMECE2021, Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, V013T14A003, November 1–5, 2021

Paper No: IMECE2021-73153

DOI: https://doi.org/10.1115/IMECE2021-73153

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Topics: Boilers, Databases, Nuclear reactors, Pressurized water reactors, Relational databases, Artificial intelligence, Eddies (Fluid dynamics), Eddy currents (Electricity), Heat transfer, Machine learning

Proceedings Papers

Nonlinear Vibrations of Beams With Bilinear Hysteresis at Supports: Interpretation of Experimental Results

Prabakaran Balasubramanian, Giulio Franchini, Giovanni Ferrari, Brian Painter, Kostas Karazis, Marco Amabili

Proc. ASME. IMECE2021, Volume 7A: Dynamics, Vibration, and Control, V07AT07A035, November 1–5, 2021

Paper No: IMECE2021-70268

DOI: https://doi.org/10.1115/IMECE2021-70268

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Topics: Vibration, Stiffness, Damping, Fuel rods, Boundary-value problems, Equations of motion, Fluids, Switches, Water, Coolants

Proceedings Papers

Composite Materials Use: A Particular Case of Safety-Related Service Water Pipes

Th. Le Courtois, M. F. Pays

Proc. ASME. IMECE99, Advances in Aerospace Materials and Structures, 139-145, November 14–19, 1999

Paper No: IMECE1999-0142

DOI: https://doi.org/10.1115/IMECE1999-0142

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Topics: Composite materials, Safety, Water pipes, Manufacturing, Pipes, Design, Nondestructive evaluation, Nuclear power stations, Circuits, Corrosion

Proceedings Papers

Survey of Research Activities for Passive Safety System of AC600

Bingde Chen, Zhumao Yang, Fuyun Ji

Proc. ASME. IMECE99, Heat Transfer: Volume 4, 267-274, November 14–19, 1999

Paper No: IMECE1999-1127

DOI: https://doi.org/10.1115/IMECE1999-1127

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Topics: Safety, Design, Containment, Cooling systems, Pressurized water reactors, Computers, Damage, Databases, Economics , Heat

Proceedings Papers

Computational Analysis of Transient 3D-Melt-Water Interactions

Nikolay Ivanov Kolev

Proc. ASME. IMECE2000, Fluids Engineering, 107-119, November 5–10, 2000

Paper No: IMECE2000-2057

DOI: https://doi.org/10.1115/IMECE2000-2057

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Topics: Transients (Dynamics), Water, Computers, Damage, Modeling, Nuclear power stations, Pressurized water reactors

Proceedings Papers

Nonlinear Vibrations of Model PWR Fuel Assemblies: Part 2 — Interpretation of Results Using Bilinear Stiffness Model

Prabakaran Balasubramanian, Giovanni Ferrari, Giulio M. Franchini, Marco Amabili, Kostas Karazis, Brian Painter

Proc. ASME. IMECE2020, Volume 7A: Dynamics, Vibration, and Control, V07AT07A031, November 16–19, 2020

Paper No: IMECE2020-24265

DOI: https://doi.org/10.1115/IMECE2020-24265

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Topics: Fuels, Pressurized water reactors, Stiffness, Vibration, Fuel rods, Boundary-value problems, Displacement, Excitation, Zirconium alloys, Computer simulation

Proceedings Papers

Nonlinear Vibrations of Model PWR Fuel Assemblies: Part 1 — Experimental Setup and Measurements

Giovanni Ferrari, Giulio Franchini, Prabakaran Balasubramanian, Kostas Karazis, Marco Amabili

Proc. ASME. IMECE2020, Volume 7A: Dynamics, Vibration, and Control, V07AT07A030, November 16–19, 2020

Paper No: IMECE2020-24235

DOI: https://doi.org/10.1115/IMECE2020-24235

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Topics: Boundary-value problems, Damping, Fuel rods, Fuels, Pressurized water reactors, Vibration

Proceedings Papers

Experiments on Nonlinear Vibrations of a Nuclear Fuel Rod Supported by Spacer Grids in Air and Submerged in Water

Marco Amabili, Prabakaran Balasubramanian, Giovanni Ferrari, Giulio M. Franchini, Francesco Giovanniello, Kostas Karazis, Brian Painter

Proc. ASME. IMECE2019, Volume 4: Dynamics, Vibration, and Control, V004T05A034, November 11–14, 2019

Paper No: IMECE2019-10663

DOI: https://doi.org/10.1115/IMECE2019-10663

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Topics: Fuel rods, Vibration, Water, Excitation, Nuclear fuels, Damping, Zirconium, Pressurized water reactors, Resonance, Safety

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NARROW

Experimental Characterization of the Nonlinear Boundary Conditions Applied by Two Different Designs of Spacer Grids on PWR Fuel Rods

Evaluation of Fuel Rod Response Using Principal Component Analysis

An Inverse Method for the Identification of a Distributed Random Excitation Acting on a Vibrating Structure: Part 2 — Flow-Induced Vibration Application

Experimental and Computational Investigation Into Vibration Wear of Control Rods in French PWRs

Flow-Induced Vibration of a Tube Array in the Inlet Region of a High Performance Steam Generator: Part 1 — Turbulence Induced Vibration

Prediction of Tube Wear due to Flow-Induced Vibration in PWR Steam Generators

CFD Analysis of Thermal Mixing and Stratification in AP600 Auxiliary Lines

Application of the W COBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis

Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head

An Efficient Finite Element Method for the Representation of Fluid Structure Interaction in Large Structural Transient Dynamic Analyses

CFD Analysis of a Direct Vessel Injection (DVI) Transient to Calculate AP600 Reactor Vessel Shell Temperatures

Uncertainty Quantification of SB LOCA With CSAU Using Optimal Statistical Estimator

A Review of SQL vs NoSQL Database for Nuclear Reactor Digital Twin Applications: With Example MongoDB Based NoSQL Database for Digital Twin Model of a Pressurized-Water-Reactor Steam-Generator

Nonlinear Vibrations of Beams With Bilinear Hysteresis at Supports: Interpretation of Experimental Results

Composite Materials Use: A Particular Case of Safety-Related Service Water Pipes

Survey of Research Activities for Passive Safety System of AC600

Computational Analysis of Transient 3D-Melt-Water Interactions

Nonlinear Vibrations of Model PWR Fuel Assemblies: Part 2 — Interpretation of Results Using Bilinear Stiffness Model

Nonlinear Vibrations of Model PWR Fuel Assemblies: Part 1 — Experimental Setup and Measurements

Experiments on Nonlinear Vibrations of a Nuclear Fuel Rod Supported by Spacer Grids in Air and Submerged in Water

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