dc.contributor.author | Forrest, Eric C | |
dc.contributor.author | Don, Sarah M. | |
dc.contributor.author | Hu, Lin-Wen | |
dc.contributor.author | Buongiorno, Jacopo | |
dc.contributor.author | McKrell, Thomas J. | |
dc.date.accessioned | 2018-07-24T18:05:22Z | |
dc.date.available | 2018-07-24T18:05:22Z | |
dc.date.issued | 2016-02 | |
dc.date.submitted | 2015-07 | |
dc.identifier.issn | 2332-8983 | |
dc.identifier.uri | http://hdl.handle.net/1721.1/117090 | |
dc.description.abstract | The 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.sponsorship | United States. Department of Energy. Office of Nonproliferation and National Security | en_US |
dc.description.sponsorship | United States. National Nuclear Security Administration. Global Threat Reduction Initiative (Contract No. #25-30101-0004A) ( | en_US |
dc.description.sponsorship | United States. National Nuclear Security Administration (contract no. DE-AC04-94AL85000) | en_US |
dc.publisher | ASME International | en_US |
dc.relation.isversionof | http://dx.doi.org/10.1115/1.4031503 | en_US |
dc.rights | Article 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.source | ASME | en_US |
dc.title | Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel | en_US |
dc.type | Article | en_US |
dc.identifier.citation | Forrest, 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.department | Massachusetts Institute of Technology. Department of Mechanical Engineering | en_US |
dc.contributor.department | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering | en_US |
dc.contributor.department | Sloan School of Management | en_US |
dc.contributor.mitauthor | Forrest, Eric C | |
dc.contributor.mitauthor | Don, Sarah M. | |
dc.contributor.mitauthor | Hu, Lin-Wen | |
dc.contributor.mitauthor | Buongiorno, Jacopo | |
dc.contributor.mitauthor | McKrell, Thomas J | |
dc.relation.journal | Journal of Nuclear Engineering and Radiation Science | en_US |
dc.eprint.version | Final published version | en_US |
dc.type.uri | http://purl.org/eprint/type/ConferencePaper | en_US |
eprint.status | http://purl.org/eprint/status/NonPeerReviewed | en_US |
dc.date.updated | 2018-07-16T16:46:25Z | |
dspace.orderedauthors | Forrest, Eric C.; Don, Sarah M.; Hu, Lin-Wen; Buongiorno, Jacopo; McKrell, Thomas J. | en_US |
dspace.embargo.terms | N | en_US |
mit.license | PUBLISHER_POLICY | en_US |