In this paper, the computational fluid dynamics (CFD) code FLUENT was used to predict wall-temperature profiles inside vertical bare tubes with supercritical water (SCW) as the cooling medium, to assess the capabilities of FLUENT for SCW heat-transfer applications. Numerical results are compared to experimental data and current one-dimensional (1D) models represented by existing heat-transfer empirical correlations. Wall-temperature and heat-transfer coefficients were analyzed to select the best model to describe the fluid flow before, at, and after the pseudocritical region. and turbulent models were evaluated in the process, with variations in the submodel parameters such as viscous heating, thermal effects, and low-Reynolds-number correction. Results of the analysis show a fit of for wall temperatures using the SST model within the deteriorated heat-transfer regime and less than within the normal heat-transfer regime. The accuracy of the model is higher than any empirical correlation tested in the mentioned regimes and provides additional information about the multidimensional effects between the bulk-fluid and wall temperatures.
Skip Nav Destination
Article navigation
July 2016
Research Papers
Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
Amjad Farah,
Amjad Farah
1
Mem. ASME
e-mail: amjad.farah@uoit.ca
Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology
, 2000 Simcoe Street North, Oshawa, ON L1J 5S1
, Canada
e-mail: amjad.farah@uoit.ca
1Corresponding author.
Search for other works by this author on:
Glenn Harvel,
Glenn Harvel
Mem. ASME
e-mail: glenn.harvel@uoit.ca
Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology
, 2000 Simcoe Street North, Oshawa, ON L1J 5S1
, Canada
e-mail: glenn.harvel@uoit.ca
Search for other works by this author on:
Igor Pioro
Igor Pioro
Mem. ASME
Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology
, 2000 Simcoe Street North, Oshawa, ON L1J 5S1
, Canada
Search for other works by this author on:
Amjad Farah
Mem. ASME
e-mail: amjad.farah@uoit.ca
Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology
, 2000 Simcoe Street North, Oshawa, ON L1J 5S1
, Canada
e-mail: amjad.farah@uoit.ca
Glenn Harvel
Mem. ASME
e-mail: glenn.harvel@uoit.ca
Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology
, 2000 Simcoe Street North, Oshawa, ON L1J 5S1
, Canada
e-mail: glenn.harvel@uoit.ca
Igor Pioro
Mem. ASME
Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology
, 2000 Simcoe Street North, Oshawa, ON L1J 5S1
, Canada
1Corresponding author.
Manuscript received August 5, 2015; final manuscript received January 14, 2016; published online June 17, 2016. Assoc. Editor: Leon Cizelj.
ASME J of Nuclear Rad Sci. Jul 2016, 2(3): 031016 (12 pages)
Published Online: June 17, 2016
Article history
Received:
August 5, 2015
Revision Received:
January 14, 2016
Accepted:
January 21, 2016
Citation
Farah, A., Harvel, G., and Pioro, I. (June 17, 2016). "Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes." ASME. ASME J of Nuclear Rad Sci. July 2016; 2(3): 031016. https://doi.org/10.1115/1.4032642
Download citation file:
Get Email Alerts
Cited By
Adjuster Absorber Rods Return To Service At Plngs
ASME J of Nuclear Rad Sci
Neutron Activation Analysis of Environmental Samples at the Training Reactor VR-1
ASME J of Nuclear Rad Sci (July 2025)
A mathematical model design for Pu content analyzed by 244Cm in spent fuel of fast reactors
ASME J of Nuclear Rad Sci
Related Articles
Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube
ASME J of Nuclear Rad Sci (July,2018)
Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes
ASME J of Nuclear Rad Sci (July,2016)
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water
ASME J of Nuclear Rad Sci (January,2018)
Related Proceedings Papers
Related Chapters
Completing the Picture
Air Engines: The History, Science, and Reality of the Perfect Engine
Scope of Section I, Organization, and Service Limits
Power Boilers: A Guide to the Section I of the ASME Boiler and Pressure Vessel Code, Second Edition
Application of Universal Functions
Applications of Mathematical Heat Transfer and Fluid Flow Models in Engineering and Medicine