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Y. F. Rao
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Proceedings Papers

Experimental Study of Coupled Thermal and Neutronic Instabilities of Two-Phase Flows in a Boiling Channel

Y. F. Rao, K. Fukuda, N. Hashii
Proc. ASME. IMECE96, Heat Transfer: Volume 2 — Heat Transfer in Turbulent Flows; Fundamentals of Convection Heat Transfer; Fundamentals of Natural Convection in Laminar and Turbulent Flows; Natural Circulation, 373-379, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0088
https://doi.org/10.1115/IMECE1996-0088
View Paper titled, Experimental Study of Coupled Thermal and Neutronic Instabilities of Two-Phase Flows in a Boiling Channel
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Topics: Boiling, Two-phase flow, Dynamics (Mechanics), Feedback, Fuels, Computers, Coolants, Heat transfer, Heating, Lumped parameter models
Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.
Paper No: NERS-19-1083
https://doi.org/10.1115/1.4046843
Published Online: June 5, 2020
View Article titled, Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
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Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling
Journal Articles

Computational Fluid Dynamics Modeling of Fire and Human Evacuation for Nuclear Applications

L. Sun, K. Podila, Q. Chen, A. M. Bayomy, Y. F. Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011112.
Paper No: NERS-19-1071
https://doi.org/10.1115/1.4044531
Published Online: November 8, 2019
View Article titled, Computational Fluid Dynamics Modeling of Fire and Human Evacuation for Nuclear Applications
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Topics: Evacuations, Fire, Simulation, Computational fluid dynamics, Smoke, Vents, Modeling
Journal Articles

A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle

M. Rohde, J. W. R. Peeters, A. Pucciarelli, A. Kiss, Y. F. Rao, E. N. Onder, P. Muehlbauer, A. Batta, M. Hartig, V. Chatoorgoon, R. Thiele, D. Chang, S. Tavoularis, D. Novog, D. McClure, M. Gradecka, K. Takase
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021012.
Paper No: NERS-15-1156
https://doi.org/10.1115/1.4031949
Published Online: February 29, 2016
View Article titled, A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle
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Topics: Flow (Dynamics), Heat transfer, Reynolds-averaged Navier–Stokes equations, Rods, Simulation, Temperature, Turbulence, Wall temperature, Water, Fuel rods
Proceedings Papers

CFD Simulation of 5×5 Rod Bundles With Split-Type Spacers

K. Podila, J. Bailey, Y. F. Rao, M. Krause
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A027, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15284
https://doi.org/10.1115/ICONE21-15284
View Paper titled, CFD Simulation of 5×5 Rod Bundles With Split-Type Spacers
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Topics: Computational fluid dynamics, Fuel rods, Simulation, Nuclear power, Turbulence, Manufacturing, Stress, Two-phase flow
Proceedings Papers

ASSERT-PV 3.2: Improved Subchannel Thermalhydraulics Code for CANDU Fuel Bundles

Y. F. Rao, Z. Cheng, G. M. Waddington, A. Nava-Dominguez
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A028, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15289
https://doi.org/10.1115/ICONE21-15289
View Paper titled, ASSERT-PV 3.2: Improved Subchannel Thermalhydraulics Code for CANDU Fuel Bundles
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Topics: Fuels, Flow (Dynamics), Critical heat flux, Heart failure, Temperature, Boiling water reactors, Flux (Metallurgy), Modeling, Nuclear industry, Nuclear power
Proceedings Papers

Assessment of Subchannel Code ASSERT-PV for Flow-Distribution Predictions

A. Nava-Dominguez, Y. F. Rao, G. M. Waddington
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A034, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15352
https://doi.org/10.1115/ICONE21-15352
View Paper titled, Assessment of Subchannel Code ASSERT-PV for Flow-Distribution Predictions
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Topics: Flow (Dynamics), Critical heat flux, Fuels, Temperature
Journal Articles

Analysis of Coupled Nuclear/Thermal Instabilities of Two-Phase Flows in Parallel Boiling Channels

M. Uehiro, Y. F. Rao, K. Fukuda
Journal: ASME Journal of Heat and Mass Transfer
Publisher: ASME
Article Type: Research Papers
J. Heat Mass Transfer. November 1999, 121(4): 916–923.
https://doi.org/10.1115/1.2826082
Published Online: November 1, 1999
View Article titled, Analysis of Coupled Nuclear/Thermal Instabilities of Two-Phase Flows in Parallel Boiling Channels
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Topics: Boiling, Two-phase flow, Stability, Computers, Diffusion (Physics), Feedback, Flow (Dynamics), Flow instability, Modeling, Multiphase flow
Journal Articles

Steady and Transient Analyses of Natural Convection in a Horizontal Porous Annulus With the Galerkin Method

Y. F. Rao, K. Fukuda, S. Hasegawa
Journal: ASME Journal of Heat and Mass Transfer
Publisher: ASME
Article Type: Research Papers
J. Heat Mass Transfer. November 1987, 109(4): 919–927.
https://doi.org/10.1115/1.3248204
Published Online: November 1, 1987
View Article titled, Steady and Transient Analyses of Natural Convection in a Horizontal Porous Annulus With the Galerkin Method
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Topics: Annulus, Galerkin method, Natural convection, Transient analysis, Heat transfer, Bifurcation, Flow (Dynamics), Transients (Dynamics)