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dc.contributor.authorForrest, Eric C
dc.contributor.authorDon, Sarah M.
dc.contributor.authorHu, Lin-Wen
dc.contributor.authorBuongiorno, Jacopo
dc.contributor.authorMcKrell, Thomas J.
dc.date.accessioned2018-07-24T18:05:22Z
dc.date.available2018-07-24T18:05:22Z
dc.date.issued2016-02
dc.date.submitted2015-07
dc.identifier.issn2332-8983
dc.identifier.urihttp://hdl.handle.net/1721.1/117090
dc.description.abstractThe onset of nucleate boiling (ONB) serves as the thermal-hydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been well-characterized in narrow channel geometries or for oxidized surface conditions. This study presents experimental data for the ONB in vertical upflow of deionized (DI) water in a simulated materials test reactor (MTR) coolant channel. The channel gap thickness and aspect ratio were 1.96 mm and 29:1, respectively. Boiling surface conditions were carefully controlled and characterized, with both heavily oxidized and native oxide surfaces tested. Measurements were performed for mass fluxes ranging from 750 to 3000 kg/m2s and for subcoolings ranging from 10 to 45°C. ONB was identified using a combination of high-speed visual observation, surface temperature measurements, and channel pressure drop measurements. Surface temperature measurements were found to be most reliable in identifying the ONB. For the nominal (native oxide) surface, results indicate that the correlation of Bergles and Rohsenow, when paired with the appropriate single-phase heat transfer correlation, adequately predicts the ONB heat flux. Incipience on the oxidized surface occurred at a higher heat flux and superheat than on the plain surface.en_US
dc.description.sponsorshipUnited States. Department of Energy. Office of Nonproliferation and National Securityen_US
dc.description.sponsorshipUnited States. National Nuclear Security Administration. Global Threat Reduction Initiative (Contract No. #25-30101-0004A) (en_US
dc.description.sponsorshipUnited States. National Nuclear Security Administration (contract no. DE-AC04-94AL85000)en_US
dc.publisherASME Internationalen_US
dc.relation.isversionofhttp://dx.doi.org/10.1115/1.4031503en_US
dc.rightsArticle is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.en_US
dc.sourceASMEen_US
dc.titleEffect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channelen_US
dc.typeArticleen_US
dc.identifier.citationForrest, Eric C., Sarah M. Don, Lin-Wen Hu, Jacopo Buongiorno, and Thomas J. McKrell. “Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel.” Journal of Nuclear Engineering and Radiation Science 2, no. 2 (February 29, 2016): 021001.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Mechanical Engineeringen_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.departmentSloan School of Managementen_US
dc.contributor.mitauthorForrest, Eric C
dc.contributor.mitauthorDon, Sarah M.
dc.contributor.mitauthorHu, Lin-Wen
dc.contributor.mitauthorBuongiorno, Jacopo
dc.contributor.mitauthorMcKrell, Thomas J
dc.relation.journalJournal of Nuclear Engineering and Radiation Scienceen_US
dc.eprint.versionFinal published versionen_US
dc.type.urihttp://purl.org/eprint/type/ConferencePaperen_US
eprint.statushttp://purl.org/eprint/status/NonPeerRevieweden_US
dc.date.updated2018-07-16T16:46:25Z
dspace.orderedauthorsForrest, Eric C.; Don, Sarah M.; Hu, Lin-Wen; Buongiorno, Jacopo; McKrell, Thomas J.en_US
dspace.embargo.termsNen_US
mit.licensePUBLISHER_POLICYen_US


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