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    Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001::page 011110-1
    Author:
    Somers-Neal, Shawn
    ,
    Nguyen, Vien
    ,
    Matida, Edgar
    ,
    Tang, Vinh
    ,
    Kaya, Tarik
    DOI: 10.1115/1.4044747
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In a reactor core meltdown under postulated severe accidents, the molten material called corium could be ejected or relocated through existing vessel penetrations. There exists, however, a potential for plugging of melt flow due to its complete solidification providing the availability of an adequate heat sink. Simulations of the melt flow in a horizontal tube were carried out to conduct a sensitivity study on the effect of key parameters on the melt penetration distance and bulk temperature distribution of the corium. The Reynolds number was varied from 10,000 to 20,000, inlet temperature was varied from 2600 K to 3000 K, the corium thermal conductivity was varied from 10 W/m·K to 20 W/m·K, and the pipe diameter was varied from 0.0095 m to 0.019 m. In addition, a comparison was made with an analytical model based on a modified Epstein's model and a previous numerical model. The study provided insight into the lower bound, which was found to be 98 mm, and the upper bound was 258 mm when predicting the potential penetration length of corium in horizontal pipes.
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      Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4275864
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorSomers-Neal, Shawn
    contributor authorNguyen, Vien
    contributor authorMatida, Edgar
    contributor authorTang, Vinh
    contributor authorKaya, Tarik
    date accessioned2022-02-04T22:59:37Z
    date available2022-02-04T22:59:37Z
    date copyright1/1/2020 12:00:00 AM
    date issued2020
    identifier issn2332-8983
    identifier otherners_006_01_011110.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275864
    description abstractIn a reactor core meltdown under postulated severe accidents, the molten material called corium could be ejected or relocated through existing vessel penetrations. There exists, however, a potential for plugging of melt flow due to its complete solidification providing the availability of an adequate heat sink. Simulations of the melt flow in a horizontal tube were carried out to conduct a sensitivity study on the effect of key parameters on the melt penetration distance and bulk temperature distribution of the corium. The Reynolds number was varied from 10,000 to 20,000, inlet temperature was varied from 2600 K to 3000 K, the corium thermal conductivity was varied from 10 W/m·K to 20 W/m·K, and the pipe diameter was varied from 0.0095 m to 0.019 m. In addition, a comparison was made with an analytical model based on a modified Epstein's model and a previous numerical model. The study provided insight into the lower bound, which was found to be 98 mm, and the upper bound was 258 mm when predicting the potential penetration length of corium in horizontal pipes.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleSensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow
    typeJournal Paper
    journal volume6
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4044747
    journal fristpage011110-1
    journal lastpage011110-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001
    contenttypeFulltext
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