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    Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 003::page 031405-1
    Author:
    Ahmed, Zayed
    ,
    Eckels, Seth
    ,
    Eckels, Steven J.
    ,
    Bindra, Hitesh
    DOI: 10.1115/1.4049280
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In case of some nuclear reactors, seawater is used as an emergency resource to remove the decay heat from the reactor core. This study aims to improve the understanding of boiling heat transfer with seawater coolants. Under the boiling conditions with seawater, the mass transfer of the dissolved impurities to the heated surface is expected to significantly impact the heat transfer characteristics. The focus of this experimental work is to measure the differences of the heat transfer performance between seawater and tapwater with electrically heated cylindrical section in a vertical annulus. High speed visualization is performed to quantify and characterize the bubble dynamics parameters. The experimental results indicate an enhanced heat transfer coefficient with seawater in the initial transient under saturated boiling followed by an asymptotic reduction to values similar to tapwater. Under subcooled boiling, a consistent reduced heat transfer coefficient was observed in seawater for a range of heat fluxes. The high speed visualization of subcooled boiling showed fewer and smaller bubbles nucleating off the heat transfer surface in seawater indicating a lower evaporative flux as compared to tapwater.
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      Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/4276538
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorAhmed, Zayed
    contributor authorEckels, Seth
    contributor authorEckels, Steven J.
    contributor authorBindra, Hitesh
    date accessioned2022-02-05T21:53:56Z
    date available2022-02-05T21:53:56Z
    date copyright4/2/2021 12:00:00 AM
    date issued2021
    identifier issn2332-8983
    identifier otherners_007_03_031405.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276538
    description abstractIn case of some nuclear reactors, seawater is used as an emergency resource to remove the decay heat from the reactor core. This study aims to improve the understanding of boiling heat transfer with seawater coolants. Under the boiling conditions with seawater, the mass transfer of the dissolved impurities to the heated surface is expected to significantly impact the heat transfer characteristics. The focus of this experimental work is to measure the differences of the heat transfer performance between seawater and tapwater with electrically heated cylindrical section in a vertical annulus. High speed visualization is performed to quantify and characterize the bubble dynamics parameters. The experimental results indicate an enhanced heat transfer coefficient with seawater in the initial transient under saturated boiling followed by an asymptotic reduction to values similar to tapwater. Under subcooled boiling, a consistent reduced heat transfer coefficient was observed in seawater for a range of heat fluxes. The high speed visualization of subcooled boiling showed fewer and smaller bubbles nucleating off the heat transfer surface in seawater indicating a lower evaporative flux as compared to tapwater.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleForced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant
    typeJournal Paper
    journal volume7
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4049280
    journal fristpage031405-1
    journal lastpage031405-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 003
    contenttypeFulltext
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