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contributor authorSaltanov, Eugene
contributor authorPioro, Igor
contributor authorMann, David
contributor authorGupta, Sahil
contributor authorMokry, Sarah
contributor authorHarvel, Glenn
date accessioned2017-05-09T01:22:17Z
date available2017-05-09T01:22:17Z
date issued2015
identifier issn2332-8983
identifier otherNERS_1_1_011008.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159284
description abstractThe appropriate description of heat transfer to coolants at the supercritical state is limited by the current understanding. Thus, this poses one of the main challenges in the development of supercriticalfluids applications for GenerationIV reactors. Since the thermodynamic critical point of water is much higher than that of carbon dioxide (CO2), it is more affordable to run heattransfer experiments in supercritical CO2. The data for supercritical CO2 can be later scaled and used for supercritical waterbased reactor designs. The objective of this paper is, therefore, to discuss the basis for comparison of relatively recent experimental data on supercritical CO2 obtained at the facilities of the Korea Atomic Energy Research Institute (KAERI) and Chalk River Laboratories (CRL) of the Atomic Energy of Canada Limited (AECL). Based on the available instrumental error, a thorough analysis of experimental errors in walland bulkfluid temperatures and heat transfer coefficient was conducted. A revised heattransfer correlation for the CRL data is presented. A dimensional criterion for the onset of the deteriorated heat transfer in the form of a linear relation between heat flux and mass flux is proposed. A preliminary heattransfer correlation for the joint CRL and KAERI datasets is presented.
publisherThe American Society of Mechanical Engineers (ASME)
titleStudy on Specifics of Forced Convective Heat Transfer in Supercritical Carbon Dioxide
typeJournal Paper
journal volume1
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4026395
journal fristpage11008
journal lastpage11008
treeJournal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001
contenttypeFulltext


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