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    An Experimental Study on Flow Boiling Heat Transfer From a Downward-Facing Finned Surface and Its Effect on Critical Heat Flux

    Source: Journal of Heat Transfer:;2018:;volume( 140 ):;issue: 002::page 21501
    Author:
    Khan, A. R.
    ,
    Erkan, N.
    ,
    Okamoto, K.
    DOI: 10.1115/1.4037154
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: During a severe accident, ex-vessel cooling may pose a risk for larger-powered reactors. The current in-vessel retention (IVR) (through ex-vessel cooling) capability may not be sufficient for the larger-powered reactors, and critical heat flux (CHF) conditions may eventually lead to vessel failure. A manner in which the CHF can be increased is by applying a structured surface design on the outer surface of the reactor pressure vessel (RPV). A simple design proposed in this work is the pin–fin. An experimental investigation was performed to observe the effect of the pin–fin on CHF with a downward-facing heated surface in flow boiling conditions. A reduced pressure of approximately 0.05 MPa allowed for saturation at approximately 81 °C. A range of flow rates corresponding to mass flux of 202–1456 kg/m2 s were applied in the experiments. The results showed an increase in the CHF when compared to a bare surface. An average CHF enhancement of 61% was observed from the finned surface. An enhancement of approximately 19% was observed in the heat transfer coefficient. As seen in nanoparticle/nanofluid enhancement, an increase in the CHF also leads to an increase in the superheat. Even though an increase in the CHF had been observed, the CHF for the finned and bare surfaces occurred at approximately similar superheat.
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      An Experimental Study on Flow Boiling Heat Transfer From a Downward-Facing Finned Surface and Its Effect on Critical Heat Flux

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    contributor authorKhan, A. R.
    contributor authorErkan, N.
    contributor authorOkamoto, K.
    date accessioned2019-02-28T11:01:01Z
    date available2019-02-28T11:01:01Z
    date copyright8/29/2017 12:00:00 AM
    date issued2018
    identifier issn0022-1481
    identifier otherht_140_02_021501.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4251756
    description abstractDuring a severe accident, ex-vessel cooling may pose a risk for larger-powered reactors. The current in-vessel retention (IVR) (through ex-vessel cooling) capability may not be sufficient for the larger-powered reactors, and critical heat flux (CHF) conditions may eventually lead to vessel failure. A manner in which the CHF can be increased is by applying a structured surface design on the outer surface of the reactor pressure vessel (RPV). A simple design proposed in this work is the pin–fin. An experimental investigation was performed to observe the effect of the pin–fin on CHF with a downward-facing heated surface in flow boiling conditions. A reduced pressure of approximately 0.05 MPa allowed for saturation at approximately 81 °C. A range of flow rates corresponding to mass flux of 202–1456 kg/m2 s were applied in the experiments. The results showed an increase in the CHF when compared to a bare surface. An average CHF enhancement of 61% was observed from the finned surface. An enhancement of approximately 19% was observed in the heat transfer coefficient. As seen in nanoparticle/nanofluid enhancement, an increase in the CHF also leads to an increase in the superheat. Even though an increase in the CHF had been observed, the CHF for the finned and bare surfaces occurred at approximately similar superheat.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleAn Experimental Study on Flow Boiling Heat Transfer From a Downward-Facing Finned Surface and Its Effect on Critical Heat Flux
    typeJournal Paper
    journal volume140
    journal issue2
    journal titleJournal of Heat Transfer
    identifier doi10.1115/1.4037154
    journal fristpage21501
    journal lastpage021501-10
    treeJournal of Heat Transfer:;2018:;volume( 140 ):;issue: 002
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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