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    Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001::page 11006
    Author:
    Chen, Yuzhou
    ,
    Zhao, Minfu
    ,
    Bi, Keming
    ,
    Yang, Bin
    ,
    Zhang, Dongxu
    ,
    Du, Kaiwen
    DOI: 10.1115/1.4038215
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Critical heat flux (CHF) experiment with uniform heating was performed in a tube of 8.2 mm in inner diameter and 2.4 m in heated length. The water flowed upward through the test section. The pressure covered the range from 8.6 to 20.8 MPa, mass flux 1157 to 3776 kg/m2s, inlet quality −2.79 to −0.08 (subcooling 19–337 °C), and local quality −0.97 to 0.53. For the pressure close to the near-critical point, the CHF decreased substantially with the pressure increasing. For the subcooling larger than a certain value, the CHF was related to the local condition. But for low subcooling and saturated condition, the CHF was related to the total power. The present results were in agreement with the previous experiment for the same local subcooled condition. Based on the present experimental results with subcooled and saturated conditions an empirical relation of the CHF was presented.
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      Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/4252549
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorChen, Yuzhou
    contributor authorZhao, Minfu
    contributor authorBi, Keming
    contributor authorYang, Bin
    contributor authorZhang, Dongxu
    contributor authorDu, Kaiwen
    date accessioned2019-02-28T11:05:21Z
    date available2019-02-28T11:05:21Z
    date copyright12/4/2017 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_01_011006.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252549
    description abstractCritical heat flux (CHF) experiment with uniform heating was performed in a tube of 8.2 mm in inner diameter and 2.4 m in heated length. The water flowed upward through the test section. The pressure covered the range from 8.6 to 20.8 MPa, mass flux 1157 to 3776 kg/m2s, inlet quality −2.79 to −0.08 (subcooling 19–337 °C), and local quality −0.97 to 0.53. For the pressure close to the near-critical point, the CHF decreased substantially with the pressure increasing. For the subcooling larger than a certain value, the CHF was related to the local condition. But for low subcooling and saturated condition, the CHF was related to the total power. The present results were in agreement with the previous experiment for the same local subcooled condition. Based on the present experimental results with subcooled and saturated conditions an empirical relation of the CHF was presented.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleCritical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction
    typeJournal Paper
    journal volume4
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4038215
    journal fristpage11006
    journal lastpage011006-5
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001
    contenttypeFulltext
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