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Proceedings Papers

Development of Three-Dimensional Velocity Vector Profiler Using Ultrasonic Pulsed Doppler Method

Naruki Shoji, Hideharu Takahashi, Hiroshige Kikura
Proc. ASME. FEDSM2022, Volume 1: Fluid Applications and Systems (FASTC); Fluid Measurement and Instrumentation (FMITC); Fluid Mechanics (FMTC), V001T02A010, August 3–5, 2022
Paper No: FEDSM2022-87878
DOI: https://doi.org/10.1115/FEDSM2022-87878
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Topics: Accidents, Algorithms, Containment vessels, Flow (Dynamics), Flow measurement, Fuels, Fukushima nuclear disaster, Japan, 2011, Inspection, Leakage, Leakage flows
Proceedings Papers

Industrial Technical Development and Qualification of Highly Efficient Stainless Steel Plates and Fins Heat Exchanger for Heat Removal Supercritical CO2 Brayton Cycle Applied to Nuclear Power Plants

Sarah Tioual-Demange, Gaëtan Bergin, Thierry Mazet, Luc de Camas
Proc. ASME. FEDSM2020, Volume 1: Fluid Applications and Systems; Fluid Measurement and Instrumentation, V001T01A008, July 13–15, 2020
Paper No: FEDSM2020-20205
DOI: https://doi.org/10.1115/FEDSM2020-20205
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Topics: Brayton cycle, Fins, Heat, Heat exchangers, Nuclear power stations, Plates (structures), Stainless steel, Supercritical carbon dioxide, Manufacturing, Alloys
Proceedings Papers

The Performance Analysis of a Reactor Coolant Pump Hydro-Static Seal in Different Operating Conditions by Reynolds Equations

Guohui Cong, Yixun Zhang, Tiejian Zhang, Kan Chen
Proc. ASME. FEDSM2017, Volume 1B, Symposia: Fluid Measurement and Instrumentation; Fluid Dynamics of Wind Energy; Renewable and Sustainable Energy Conversion; Energy and Process Engineering; Microfluidics and Nanofluidics; Development and Applications in Computational Fluid Dynamics; DNS/LES and Hybrid RANS/LES Methods, V01BT09A004, July 30–August 3, 2017
Paper No: FEDSM2017-69479
DOI: https://doi.org/10.1115/FEDSM2017-69479
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Topics: Nuclear reactor coolants, Pumps, Pressure, Leakage, Temperature, Centrifugal force, Design, Fluids, High temperature, Nuclear power stations
Proceedings Papers

Research on Heat-Transfer and Cooling Performance of Gas Turbine Endwall

Kazuto Kakio, Y. Kawata
Proc. ASME. FEDSM2017, Volume 1A, Symposia: Keynotes; Advances in Numerical Modeling for Turbomachinery Flow Optimization; Fluid Machinery; Industrial and Environmental Applications of Fluid Mechanics; Pumping Machinery, V01AT03A016, July 30–August 3, 2017
Paper No: FEDSM2017-69245
DOI: https://doi.org/10.1115/FEDSM2017-69245
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Topics: Cooling, Gas turbines, Heat transfer, Blades, Pressure gradient, Flow (Dynamics), Turbine blades, Vortices, Boundary layers, Combined cycle power stations
Proceedings Papers

Pool Scrubbing Efficiency of Hypothesized Filtered Containment Venting System for APR1400 Nuclear Power Plants

Seungwon Seo, Jungjae Lee, Yongjin Cho
Proc. ASME. FEDSM2017, Volume 1B, Symposia: Fluid Measurement and Instrumentation; Fluid Dynamics of Wind Energy; Renewable and Sustainable Energy Conversion; Energy and Process Engineering; Microfluidics and Nanofluidics; Development and Applications in Computational Fluid Dynamics; DNS/LES and Hybrid RANS/LES Methods, V01BT09A002, July 30–August 3, 2017
Paper No: FEDSM2017-69387
DOI: https://doi.org/10.1115/FEDSM2017-69387
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Topics: Containment, Nuclear power stations, Accidents, Aerosols, Containment buildings, Decontamination, Pressure, Radioactive substances, Steam, Cooling
Proceedings Papers

Parametric Investigation on the Effect Factors for Liquid Droplet Impingement Erosion

Rui Li, Hisashi Ninokata, Michitsugu Mori
Proc. ASME. AJK2011, ASME-JSME-KSME 2011 Joint Fluids Engineering Conference: Volume 1, Symposia – Parts A, B, C, and D, 1347-1355, July 24–29, 2011
Paper No: AJK2011-03034
DOI: https://doi.org/10.1115/AJK2011-03034
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Topics: Drops, Erosion, Pipes, Accidents, Algorithms, Computational fluid dynamics, Computer simulation, Engineers, Fluids, Geometry
Proceedings Papers

Investigation of Rod Vibrations in Droplet Two-Phase Flows

Yoshiteru Komuro, Zensaku Kawara, Tomoaki Kunugi
Proc. ASME. AJK2011, ASME-JSME-KSME 2011 Joint Fluids Engineering Conference: Volume 1, Symposia – Parts A, B, C, and D, 2081-2089, July 24–29, 2011
Paper No: AJK2011-08001
DOI: https://doi.org/10.1115/AJK2011-08001
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Topics: Drops, Two-phase flow, Vibration, Computer simulation, Air flow, Computer software, Displacement, Flow-induced vibrations, Nuclear power stations, Safety
Proceedings Papers

A Study on the Cause Investigation of the Local Pipe Wall Thinning in the Downstream of an Orifice Through the UT Data and Numerical Analysis

Kyeong Mo Hwang, Hun Yun, Chan Kyoo Lee
Proc. ASME. AJK2011, ASME-JSME-KSME 2011 Joint Fluids Engineering Conference: Volume 2, Fora, 219-224, July 24–29, 2011
Paper No: AJK2011-33014
DOI: https://doi.org/10.1115/AJK2011-33014
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Topics: Numerical analysis, Pipes, Cavitation, Flow (Dynamics), Wear, Bubbles, Damage, Nuclear power stations, Piping systems, Shock (Mechanics)
Proceedings Papers

Best Estimate Plus Uncertainty Analysis of LBLOCA for a Pickering B CANDU Reactor

Larry Blake, George Gavrus, Jack Vecchiarelli, J. Stoklosa
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1463-1472, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31018
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31018
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Topics: Accidents, Coolants, Fuels, Nuclear industry, Nuclear power stations, Power stations, Pressure, Response surface methodology, Safety, Sensitivity analysis
Proceedings Papers

Reformulation RELAP5-3D in FORTRAN 95 and Results

George L. Mesina
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1959-1968, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-30401
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-30401
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Topics: FORTRAN, Machinery, Computer programming, Databases, Design, Fluids, Maintenance, Manifolds, Nuclear power stations, Safety
Proceedings Papers

Application of Uncertainty Analysis in the Comparison of Void Fraction Calculations With Experiment

Jason Pascoe, Yuksel Parlatan, B. McLaughlin, Sophia Fung
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1473-1482, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31027
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31027
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Topics: Porosity, Uncertainty analysis, Uncertainty, Computers, Coolants, Accidents, Modeling, Design, Engineering simulation, Nuclear power stations
Proceedings Papers

Uncertainty Analysis Becoming Common Practice in Safety Assessment

Horst G. Glaeser
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1483-1491, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31179
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31179
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Topics: Safety, Uncertainty analysis, Uncertainty, Licensing, Acceptance criteria, Computers, Accidents, Containment, Fuel rods, Nuclear power stations
Proceedings Papers

The BEPU Challenge in Current Licensing of Nuclear Reactors

F. D’Auria, A. Petruzzi, N. Muellner, O. Mazzantini
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1511-1517, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31279
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31279
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Topics: Licensing, Nuclear reactors, Uncertainty, Heavy water reactors, Nuclear power stations, Safety
Proceedings Papers

CFD Simulation of Proposed Validation Data for a Flow Problem Reconfigured to Eliminate an Undesirable Flow Instability

Richard W. Johnson, Hugh M. McIlroy
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 2259-2264, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-30522
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-30522
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Topics: Computational fluid dynamics, Flow (Dynamics), Flow instability, Simulation, Very high temperature reactors, Design, Helium, Jets, Safety, Computation
Proceedings Papers

Fluidelastic Instability of a Single Flexible Tube in a Rigid Tube Array

Ahmed Khalifa, David Weaver, Samir Ziada
Proc. ASME. FEDSM2010, ASME 2010 7th International Symposium on Fluid-Structure Interactions, Flow-Sound Interactions, and Flow-Induced Vibration and Noise: Volume 3, Parts A and B, 383-394, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-30030
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-30030
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Topics: Excitation, Failure, Fluid structure interaction, Geometry, Heat exchangers, Nuclear power stations, Shells, Stability, Vibration
Proceedings Papers

Experimental Study of Dynamic Interaction Between a Steam Generator Tube and an Anti-Vibration Bar

V. Lalonde, A. Ross, M. J. Pettigrew, I. Nowlan
Proc. ASME. FEDSM2010, ASME 2010 7th International Symposium on Fluid-Structure Interactions, Flow-Sound Interactions, and Flow-Induced Vibration and Noise: Volume 3, Parts A and B, 661-670, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31017
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31017
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Topics: Boilers, Vibration, Clearances (Engineering), Excitation, Wear, Abrasion, Cross-flow, Damage, Damping, Flow-induced vibrations
Proceedings Papers

Simulation of Fluid Flow Using Reduced-Order Modeling by POD Approach Applied to a Fixed Tube Bundle System

Marie Pomarede, Erwan Liberge, Aziz Hamdouni, Elisabeth Longatte, Jean-Franc¸ois Sigrist
Proc. ASME. FEDSM2010, ASME 2010 7th International Symposium on Fluid-Structure Interactions, Flow-Sound Interactions, and Flow-Induced Vibration and Noise: Volume 3, Parts A and B, 259-268, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-30133
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-30133
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Topics: Boilers, Computation, Degrees of freedom, Dynamic analysis, Flow (Dynamics), Fluid dynamics, Fluid structure interaction, Fluids, Modeling, Nuclear power stations
Proceedings Papers

TITRAM Fast Transient Licensing Analysis Methodology for Kuosheng BWR/6

Jan-Ru Tang, Hon-Chin Jien, Yang-Kai Chiu, Cheng-Der Wang, Julian S. C. Chian
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1533-1543, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31281
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31281
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Topics: Boiling water reactors, Licensing, Transients (Dynamics), Uncertainty, Transient analysis, Safety, Construction, Nuclear energy research, Nuclear industry, Nuclear power stations
Proceedings Papers

IAEA SSG-2: Deterministic Safety Analysis for NPP

M. Dusic, F. D’Auria, A. Petruzzi, L. M. C. Dutton, H. Glaeser, B. Mavko, F. Pelayo
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1553-1562, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31285
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31285
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Topics: Nuclear power stations, Safety, Accidents, Emergencies, Hazards, Radiation (Physics)
Proceedings Papers

BEPU Methodologies and Plant Technical Specifications

R. Mendiza´bal, F. Pelayo
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1573-1579, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-31289
DOI: https://doi.org/10.1115/FEDSM-ICNMM2010-31289
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Topics: Licensing, Nuclear power stations, Safety, Surveillance, Uncertainty, Uncertainty analysis