The results of heat transfer to supercritical water flowing upward in a vertical tight 7-rod bundle consisting of tubes of 5.2-mm outside diameter and 485-mm heated length are presented. The heat-transfer data were obtained at pressures of 22.5, 24.5, and 27.5 MPa, mass flux within the range from 700 to 1500 kg/m2s, inlet temperature from 125 to 325°C, outlet temperature up to 379°C and heat flux up to 1.6 MW/m2 (heat flux rate up to 1.5 kJ/kg). Temperature regimes of the bundle cooled by supercritical water were stable and easily reproducible within the whole range of the mass and heat fluxes, even when a deteriorated heat transfer took place. The data resulted from the study could be applicable for a reference estimation of heat transfer in future designs of the fuel bundles.
Skip Nav Destination
16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4816-7
PROCEEDINGS PAPER
Heat Transfer to Supercritical Water in Vertical 7-Rod Bundle
V. G. Razumovskiy,
V. G. Razumovskiy
National Technological University of Ukraine “KPI”, Kyiv, Ukraine
Search for other works by this author on:
E. N. Pis’mennyy,
E. N. Pis’mennyy
National Technological University of Ukraine “KPI”, Kyiv, Ukraine
Search for other works by this author on:
A. E. Koloskov,
A. E. Koloskov
National Technological University of Ukraine “KPI”, Kyiv, Ukraine
Search for other works by this author on:
I. L. Pioro
I. L. Pioro
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
V. G. Razumovskiy
National Technological University of Ukraine “KPI”, Kyiv, Ukraine
E. N. Pis’mennyy
National Technological University of Ukraine “KPI”, Kyiv, Ukraine
A. E. Koloskov
National Technological University of Ukraine “KPI”, Kyiv, Ukraine
I. L. Pioro
University of Ontario Institute of Technology, Oshawa, ON, Canada
Paper No:
ICONE16-48954, pp. 963-969; 7 pages
Published Online:
June 24, 2009
Citation
Razumovskiy, VG, Pis’mennyy, EN, Koloskov, AE, & Pioro, IL. "Heat Transfer to Supercritical Water in Vertical 7-Rod Bundle." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Instrumentation and Controls. Orlando, Florida, USA. May 11–15, 2008. pp. 963-969. ASME. https://doi.org/10.1115/ICONE16-48954
Download citation file:
36
Views
Related Proceedings Papers
Related Articles
Experiment of Heat Transfer to Supercritical Water Flowing in Vertical Annular Channels
J. Heat Transfer (April,2013)
Forced Convection Heat Transfer From an Isothermal Sphere to Water
J. Heat Transfer (May,1961)
Replacing All Fossil Fuels With Nuclear-Enabled Hydrogen, Cellulosic Hydrocarbon Biofuels, and Dispatchable Electricity
ASME Open J. Engineering (January,2024)
Related Chapters
Introduction
Heat Transfer & Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications
Summary
Heat Transfer & Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications
Nuclear Power Reactors and Their Fuels
Fundamentals of Nuclear Fuel