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dc.contributor.authorSu, G.- Y.
dc.contributor.authorPhillips, Bren Andrew
dc.contributor.authorBuongiorno, Jacopo
dc.date.accessioned2020-08-24T17:48:44Z
dc.date.available2020-08-24T17:48:44Z
dc.date.issued2019-08
dc.identifier.isbn9780894487675
dc.identifier.urihttps://hdl.handle.net/1721.1/126760
dc.description.abstractSimultaneous measurement of liquid film characteristics and heat transfer in annular two-phase flow is a major experimental challenge. In this study, we implement an innovative integrated infrared (IR) heater and liquid film electrical-conductance sensor in combination with high-speed IR thermography, which results in an accurate, synchronized and co-located measurement of liquid film characteristics and local heat transfer at the heated surface in diabatic annular two-phase flow. The measurements reveal that disturbance waves have a significant effect on the instantaneous heat transfer response in nominally-steady vertically upward annular flow of steam-water mixtures. Although the heat flux applied at the wall is constant in time, the passage of the waves causes significant periodic oscillations of the local heat transfer coefficient and wall superheat in the forced convective evaporation regime, which are reported in this study.en_US
dc.language.isoen
dc.publisherAmerican Nuclear Societyen_US
dc.rightsCreative Commons Attribution-Noncommercial-Share Alikeen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-sa/4.0/en_US
dc.sourceProf. Buongiorno via Chris Sherratten_US
dc.titleUnexpected heat transfer oscillations in steady annular flow detected by synchronized infrared and liquid film sensor measurementsen_US
dc.typeArticleen_US
dc.identifier.citationSu, G.- Y. et al. “Unexpected heat transfer oscillations in steady annular flow detected by synchronized infrared and liquid film sensor measurements.” 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, (August 2019): 5709 - 5715 © 2019 The Author(s)en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.relation.journal18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019en_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/ConferencePaperen_US
eprint.statushttp://purl.org/eprint/status/NonPeerRevieweden_US
dc.date.updated2020-08-21T12:04:01Z
dspace.date.submission2020-08-21T12:04:03Z
mit.licenseOPEN_ACCESS_POLICY
mit.metadata.statusComplete


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