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A. Nava-Dominguez
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Journal Articles

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

A. Nava-Dominguez
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.
Paper No: NERS-19-1082
https://doi.org/10.1115/1.4046783
Published Online: June 5, 2020
View Article titled, Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR
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Topics: Flow (Dynamics), Friction, Pressure drop, Wire, Fuels, Water, Supercritical water reactors, Manufacturing, Pipes
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
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

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

T. Beuthe, A. Vasić, H. Zahlan, A. Nava Domínguez
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115.
Paper No: NERS-20-1002
https://doi.org/10.1115/1.4047288
Published Online: June 5, 2020
View Article titled, Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors
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Topics: Heat transfer, Modeling, Pressure, Supercritical water reactors, Temperature, Simulation, Accidents, Testing, Water, Transients (Dynamics)
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
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
Open the PDF for ASSERT-PV 3.2: Improved Subchannel Thermalhydraulics Code for CANDU Fuel Bundles in another window
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
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