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Stephen D. Smith
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Journal Articles

Mechanics Informed Neutron Noise Monitoring to Perform Remote Condition Assessment for Reactor Vessel Internals

Gregory A. Banyay, Matthew J. Palamara, Jessica N. Preston, Stephen D. Smith
Journal: ASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg
Article Type: Research-Article
ASME J. Risk Uncertainty Part B. December 2022, 8(4): 041104.
Paper No: RISK-21-1048
https://doi.org/10.1115/1.4054444
Published Online: June 2, 2022
View Article titled, Mechanics Informed Neutron Noise Monitoring to Perform Remote Condition Assessment for Reactor Vessel Internals
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Topics: Bending (Stress), Finite element model, Heat shielding, Mode shapes, Neutrons, Noise (Sound), Reactor vessels, Structural health monitoring, Signals, Finite element analysis
Proceedings Papers

Coupling of Neutron Noise and Dynamic Finite Element Analyses to Perform Remote Condition Monitoring for Reactor Vessel Internals

Gregory A. Banyay, Matthew J. Palamara, Stephen D. Smith
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A006, July 13–15, 2021
Paper No: PVP2021-62201
https://doi.org/10.1115/PVP2021-62201
View Paper titled, Coupling of Neutron Noise and Dynamic Finite Element Analyses to Perform Remote Condition Monitoring for Reactor Vessel Internals
Open the PDF for Coupling of Neutron Noise and Dynamic Finite Element Analyses to Perform Remote Condition Monitoring for Reactor Vessel Internals in another window
Topics: Condition monitoring, Finite element analysis, Heat shielding, Machine learning, Neutrons, Noise (Sound), Reactor vessels, Structural dynamics, Structural health monitoring
Proceedings Papers

Vibration of a High Energy PWR Piping System due to Vibro-Acoustic Coupling: Evaluation and Mitigation

Gregory A. Meyer, Timothy K. Meneely, Jeremy R. Koether, Stephen D. Smith, David C. DiBasilio
Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A021, July 14–19, 2019
Paper No: PVP2019-93594
https://doi.org/10.1115/PVP2019-93594
View Paper titled, Vibration of a High Energy PWR Piping System due to Vibro-Acoustic Coupling: Evaluation and Mitigation
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Topics: Acoustics, Piping systems, Pressurized water reactors, Vibration, Pipes, Flow (Dynamics), Resonance, Boiling water reactors, Excitation, Junctions
Proceedings Papers

Sensitivity Analysis of a Nuclear Reactor System Finite Element Model

Gregory A. Banyay, Stephen D. Smith, Jason S. Young
Proc. ASME. VVS2018, ASME 2018 Verification and Validation Symposium, V001T04A001, May 16–18, 2018
Paper No: VVS2018-9306
https://doi.org/10.1115/VVS2018-9306
View Paper titled, Sensitivity Analysis of a Nuclear Reactor System Finite Element Model
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Topics: Finite element model, Nuclear reactors, Sensitivity analysis, Pressurized water reactors, Uncertainty, Accidents, Construction, Coolants, Design, Earthquakes
Proceedings Papers

Development of an Advanced PWR Reactor Internals System Finite Element Model for Flow-Induced Vibration Analyses

Matthew J. Palamara, Stephen D. Smith, Adam P. Walker, Richard A. Basel, Gregory A. Meyer
Proc. ASME. PVP2015, Volume 4: Fluid-Structure Interaction, V004T04A026, July 19–23, 2015
Paper No: PVP2015-45278
https://doi.org/10.1115/PVP2015-45278
View Paper titled, Development of an Advanced PWR Reactor Internals System Finite Element Model for Flow-Induced Vibration Analyses
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Topics: Finite element model, Flow-induced vibrations, Pressurized water reactors, Computer simulation, Reactor vessels, Turbulence, Coolants, Dynamic response, Excitation, Finite element analysis