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    Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002::page 21001
    Author:
    Forrest, Eric C.
    ,
    Don, Sarah M.
    ,
    Hu, Lin
    ,
    Buongiorno, Jacopo
    ,
    McKrell, Thomas J.
    DOI: 10.1115/1.4031503
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The onset of nucleate boiling (ONB) serves as the thermalhydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been wellcharacterized 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 1.96آ 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/m2 s and for subcoolings ranging from 10 to 45آ°C. ONB was identified using a combination of highspeed 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 singlephase 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.
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      Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

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    http://yetl.yabesh.ir/yetl1/handle/yetl/162199
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorForrest, Eric C.
    contributor authorDon, Sarah M.
    contributor authorHu, Lin
    contributor authorBuongiorno, Jacopo
    contributor authorMcKrell, Thomas J.
    date accessioned2017-05-09T01:32:12Z
    date available2017-05-09T01:32:12Z
    date issued2016
    identifier issn2332-8983
    identifier otherNERS_2_2_021001.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162199
    description abstractThe onset of nucleate boiling (ONB) serves as the thermalhydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been wellcharacterized 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 1.96آ 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/m2 s and for subcoolings ranging from 10 to 45آ°C. ONB was identified using a combination of highspeed 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 singlephase 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.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEffect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel
    typeJournal Paper
    journal volume2
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4031503
    journal fristpage21001
    journal lastpage21001
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002
    contenttypeFulltext
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