Show simple item record

contributor authorRazumovskiy, V. G.
contributor authorPis’mennyi, Eu. N.
contributor authorSidawi, Kh.
contributor authorPioro, I. L.
contributor authorKoloskov, A. Eu.
date accessioned2017-05-09T01:32:13Z
date available2017-05-09T01:32:13Z
date issued2016
identifier issn2332-8983
identifier otherNERS_2_1_011010.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162209
description abstractThere 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 3rod bundle (rods are also equipped with four helical ribs) are discussed. The experimental results include bulkfluidtemperature, walltemperature, and heattransfercoefficient (HTC) profiles along the heated length (485آ mm) for these flow geometries. Data obtained from this study could be applicable as a reference estimation of heat transfer for future fuelbundle designs.
publisherThe American Society of Mechanical Engineers (ASME)
titleExperimental Heat Transfer in an Annular Channel and 3 Rod Bundle Cooled With Upward Flow of Supercritical Water
typeJournal Paper
journal volume2
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4031818
journal fristpage11010
journal lastpage11010
treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001
contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record