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Heat Transfer to Supercritical Water in Vertical 7-Rod Bundle

[+] Author Affiliations
V. G. Razumovskiy, E. N. Pis’mennyy, 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
  • 16th International Conference on Nuclear Engineering
  • Volume 3: Thermal Hydraulics; Instrumentation and Controls
  • Orlando, Florida, USA, May 11–15, 2008
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4816-7 | eISBN: 0-7918-3820-X
  • Copyright © 2008 by ASME


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/m2 s, 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.

Copyright © 2008 by ASME
Topics: Heat transfer , Water



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