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dc.contributor.authorSu, Guanyu
dc.contributor.authorBucci, Matteo
dc.contributor.authorBuongiorno, Jacopo
dc.contributor.authorMcKrell, Thomas J.
dc.date.accessioned2017-04-20T20:25:32Z
dc.date.available2017-04-20T20:25:32Z
dc.date.issued2016-01
dc.date.submitted2015-08
dc.identifier.isbn9781510811843
dc.identifier.urihttp://hdl.handle.net/1721.1/108321
dc.description.abstractThis paper presents an investigation of transient pool boiling heat transfer phenomena for water at atmospheric pressure under rapidly escalating heat fluxes on plate-type heaters, which were used to simulate the interface between cladding and coolant in plate-type fuel during Reactivity Initiated Accidents (RIAs). The investigation utilized Infrared (IR) thermometry and High-Speed Video (HSV) to gain insight into the physical phenomena and generate a database that can be used for development and validation of accurate models of transient boiling heat transfer. The test matrix included exponential power escalations with periods in the range from 5 to 100 milliseconds, and subcooling of 0, 25 and 75 K. The onset of nucleate boiling (ONB), onset of significant void (OSV) and overshoot (OV) conditions were identified. The experimental data suggest that ONB, OSV and OV temperature and heat flux increase monotonically with decreasing period and increasing subcooling. The transient boiling curves were measured up to the fully developed nucleate boiling (FDNB) regime.en_US
dc.language.isoen_US
dc.publisherAmerican Nuclear Societyen_US
dc.relation.isversionofhttp://www.proceedings.com/27758.htmlen_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.titleExperimental Study of Heat Transfer Mechanisms under Exponential Power Excursion in Plate-Type Fuelen_US
dc.typeArticleen_US
dc.identifier.citationSu, G. et al. "Experimental Study of Heat Transfer Mechanisms under Exponential Power Excursion in Plate-Type Fuel." International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015 (NURETH-16), 30 August-4 September, 2015, American Nuclear Society, 2016. pp. 3111-2123.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.approverBuongiornoen_US
dc.contributor.mitauthorSu, Guanyu
dc.contributor.mitauthorBucci, Matteo
dc.contributor.mitauthorMcKrell, Thomas J
dc.contributor.mitauthorBuongiorno, Jacopo
dc.relation.journalProceedings of the International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015 (NURETH-16)en_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
dspace.orderedauthorsSu, G; Bucci, M.; McKrell, T. J.; Buongiorno, J.en_US
dspace.embargo.termsNen_US
dc.identifier.orcidhttps://orcid.org/0000-0002-6544-4943
mit.licenseOPEN_ACCESS_POLICYen_US


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