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dc.contributor.authorDeev, V. I.
dc.contributor.authorKharitonov, V. S.
dc.contributor.authorBaisov, A. M.
dc.contributor.authorChurkin, A. N.
dc.date.accessioned2022-02-04T14:26:50Z
dc.date.available2022-02-04T14:26:50Z
dc.date.copyright2020/02/24/
dc.date.issued2020
dc.identifier.issn2332-8983
dc.identifier.otherners_006_02_021109.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4273675
dc.description.abstractThe paper contains the results of analysis of heat transfer regimes in the case of forced turbulent flow of water and modeling fluids in channels of various configurations at supercritical pressures. Two new complex criteria were proposed for describing heat transfer in the pseudo-phase transition region. A system of equations suitable for the engineering calculation of heat transfer in fuel assemblies of nuclear supercritical water reactors is presented. A comparison of the calculations of heat transfer coefficient (HTC) with experimental data for the regimes of normal, deteriorated and mixed heat transfer is made.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleA New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region
dc.typeJournal Paper
dc.journal.volume6
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4046112
dc.page21109
dc.treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002
dc.contenttypeFulltext


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