There have been relatively few publications detailing heat transfer to supercritical water (SCW) flowing through a channel with a bundle or just with a single rod (annular channel) as compared to heat transfer to SCW in bare tubes. In the present paper, results of experimental heat transfer to SCW flowing upward in an annular channel with a heated rod equipped with four helical ribs and a 3-rod bundle (rods are also equipped with four helical ribs) are discussed. The experimental results include bulk-fluid-temperature, wall-temperature, and heat-transfer-coefficient (HTC) profiles along the heated length (485 mm) for these flow geometries. Data obtained from this study could be applicable as a reference estimation of heat transfer for future fuel-bundle designs.
Experimental Heat Transfer in an Annular Channel and 3-Rod Bundle Cooled With Upward Flow of Supercritical Water
Manuscript received June 23, 2015; final manuscript received October 5, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.
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Razumovskiy, V. G., Pis’mennyi, E. N., Sidawi, K., Pioro, I. L., and Koloskov, A. E. (December 9, 2015). "Experimental Heat Transfer in an Annular Channel and 3-Rod Bundle Cooled With Upward Flow of Supercritical Water." ASME. ASME J of Nuclear Rad Sci. January 2016; 2(1): 011010. https://doi.org/10.1115/1.4031818
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