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Proceedings Papers

Application of Sparse Estimation for Best Estimate Plus Uncertainty Analysis of a Small Break LOCA in PWRs

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Ikuo Kinoshita
Proc. ASME. IMECE2023, Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis, V013T15A017, October 29–November 2, 2023
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2023-111094
https://doi.org/10.1115/IMECE2023-111094
View Paper titled, Application of Sparse Estimation for Best Estimate Plus Uncertainty Analysis of a Small Break LOCA in PWRs
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Topics: Loss of coolant accidents, Pressurized water reactors, Uncertainty analysis, Cladding systems (Building), Errors, Polynomials, Regression models, Temperature, Uncertainty, Uncertainty quantification
Proceedings Papers

Investigation of Bleed-and-Feed Procedures for Mitigating the Consequence of a Total Loss-of-Feedwater Transient: IIST Experiments

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C. H. Lee, T. J. Liu, C. Y. Chang, W. T. Hong, Y. K. Chan, I. M. Hwang, C. J. Chang
Proc. ASME. IMECE96, Thermal Science of Advanced Steam Generators/Heat Exchangers, 23-29, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0763
https://doi.org/10.1115/IMECE1996-0763
View Paper titled, Investigation of Bleed-and-Feed Procedures for Mitigating the Consequence of a Total Loss-of-Feedwater Transient: IIST Experiments
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Topics: Feedwater, Transients (Dynamics), Pressurized water reactors, Nuclear energy research, Nuclear reactor coolants, Pressure, Thermal hydraulics
Proceedings Papers

Experimental Study on PORV Stuck-Open Accident in INER Integral System Test Facility

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T. J. Liu, C. H. Lee, W. T. Hong, Y. K. Chan, C. Y. Chang
Proc. ASME. IMECE96, Heat Transfer: Volume 3 — Experimental Studies in Multiphase Flow; Multiphase Flow in Porous Media; Experimental Multiphase Flows and Numerical Simulation of Two-Phase Flows; Fundamental Aspects of Experimental Methods, 123-130, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0102
https://doi.org/10.1115/IMECE1996-0102
View Paper titled, Experimental Study on PORV Stuck-Open Accident in INER Integral System Test Facility
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Topics: Accidents, Test facilities, Cooling, High pressure (Physics), Loss of coolant accidents, Pressurized water reactors, Safety, Boilers, Emergency core cooling systems, Emergency operating procedures
Proceedings Papers

Analyses of Containment Structures With Corrosion Damage

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Jeffery L. Cherry
Proc. ASME. IMECE96, Development, Validation, and Application of Inelastic Methods for Structural Analysis and Design, 15-23, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0554
https://doi.org/10.1115/IMECE1996-0554
View Paper titled, Analyses of Containment Structures With Corrosion Damage
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Topics: Containment, Corrosion, Damage, Failure, Steel, Carbon, Condensers (steam plant), Finite element analysis, Ice, Materials properties
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2022-96787
https://doi.org/10.1115/IMECE2022-96787
View Paper titled, Experimental Characterization of the Nonlinear Boundary Conditions Applied by Two Different Designs of Spacer Grids on PWR Fuel Rods
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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

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Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis
Proc. ASME. IMECE2022, Volume 5: Dynamics, Vibration, and Control, V005T07A043, October 30–November 3, 2022
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2022-96808
https://doi.org/10.1115/IMECE2022-96808
View Paper titled, Evaluation of Fuel Rod Response Using Principal Component Analysis
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0075
https://doi.org/10.1115/IMECE1997-0075
View Paper titled, An Inverse Method for the Identification of a Distributed Random Excitation Acting on a Vibrating Structure: Part 2 — Flow-Induced Vibration Application
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0118
https://doi.org/10.1115/IMECE1997-0118
View Paper titled, Experimental and Computational Investigation Into Vibration Wear of Control Rods in French PWRs
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0124
https://doi.org/10.1115/IMECE1997-0124
View Paper titled, Flow-Induced Vibration of a Tube Array in the Inlet Region of a High Performance Steam Generator: Part 1 — Turbulence Induced Vibration
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0119
https://doi.org/10.1115/IMECE1997-0119
View Paper titled, Prediction of Tube Wear due to Flow-Induced Vibration in PWR Steam Generators
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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

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Alexander W. Harkness, Richard E. Schwirian, Petr Dymacek
Proc. ASME. IMECE97, Nuclear Engineering, 115-122, November 16–21, 1997
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0614
https://doi.org/10.1115/IMECE1997-0614
View Paper titled, CFD Analysis of Thermal Mixing and Stratification in AP600 Auxiliary Lines
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0603
https://doi.org/10.1115/IMECE1997-0603
View Paper titled, Application of the W COBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis
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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

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R. E. Schwirian
Proc. ASME. IMECE97, Nuclear Engineering, 65-70, November 16–21, 1997
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1997-0608
https://doi.org/10.1115/IMECE1997-0608
View Paper titled, Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head
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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

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Alexander W. Harkness, Richard E. Schwirian
Proc. ASME. IMECE98, Fluids Engineering, 145-152, November 15–20, 1998
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1998-0997
https://doi.org/10.1115/IMECE1998-0997
View Paper titled, An Efficient Finite Element Method for the Representation of Fluid Structure Interaction in Large Structural Transient Dynamic Analyses
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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

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John C. Matarazzo, Richard E. Schwirian
Proc. ASME. IMECE98, Nuclear Engineering, 1-7, November 15–20, 1998
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1998-1127
https://doi.org/10.1115/IMECE1998-1127
View Paper titled, CFD Analysis of a Direct Vessel Injection (DVI) Transient to Calculate AP600 Reactor Vessel Shell Temperatures
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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

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Andrej Prošek, Borut Mavko
Proc. ASME. IMECE98, Nuclear Engineering, 15-21, November 15–20, 1998
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1998-1129
https://doi.org/10.1115/IMECE1998-1129
View Paper titled, Uncertainty Quantification of SB LOCA With CSAU Using Optimal Statistical Estimator
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Topics: Uncertainty quantification, Uncertainty, Accidents, Coolants, Safety, Algorithms, Cladding systems (Building), Computers, Pressurized water reactors, Response surface methodology
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2021-70268
https://doi.org/10.1115/IMECE2021-70268
View Paper titled, Nonlinear Vibrations of Beams With Bilinear Hysteresis at Supports: Interpretation of Experimental Results
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Topics: Vibration, Stiffness, Damping, Fuel rods, Boundary-value problems, Equations of motion, Fluids, Switches, Water, Coolants
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2021-73153
https://doi.org/10.1115/IMECE2021-73153
View Paper titled, 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
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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

Survey of Research Activities for Passive Safety System of AC600

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Bingde Chen, Zhumao Yang, Fuyun Ji
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 267-274, November 14–19, 1999
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1999-1127
https://doi.org/10.1115/IMECE1999-1127
View Paper titled, Survey of Research Activities for Passive Safety System of AC600
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Topics: Safety, Design, Containment, Cooling systems, Pressurized water reactors, Computers, Damage, Databases, Economics , Heat
Proceedings Papers

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

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Th. Le Courtois, M. F. Pays
Proc. ASME. IMECE99, Advances in Aerospace Materials and Structures, 139-145, November 14–19, 1999
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1999-0142
https://doi.org/10.1115/IMECE1999-0142
View Paper titled, Composite Materials Use: A Particular Case of Safety-Related Service Water Pipes
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Topics: Composite materials, Safety, Water pipes, Manufacturing, Pipes, Design, Nondestructive evaluation, Nuclear power stations, Circuits, Corrosion