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    Experimental Investigation of Melt Coolability Behavior in an ExVessel Core Catcher: The Effect of Flooding Time

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003::page 31401
    Author:
    V, Ganesh;Kulkarni, Parimal P.;Nayak, Arun K.
    DOI: 10.1115/1.4053220
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Some of the advanced nuclear reactors employ an exvessel core catcher to mitigate core melt scenarios by stabilizing and cooling the corium for a prolonged period by strategically flooding it. The side indirect cooling with top flooding strategy described in this study may lead to water ingression through the melt crust, which may lead to interaction between unoxidized metal and water, leading to hydrogen production. In order to avoid this deleterious scenario, water ingression into the interior region of the melt should be avoided. The studies described in this paper show that water ingression depends on the flooding strategy, i.e., the time delay between top flooding and melt relocation. Two experiments under identical conditions of simulant temperature, melt material, and test section geometry were conducted with simulated decay heat of 1 MW/m3. Sodium borosilicate glass was used as the corium simulant. In the first experiment, water was flooded onto the top of melt pool soon after melt relocation. In the second experiment, water flooding at the top of melt pool was made after 30 min of the melt relocation. The results show that a finite time delay of introduction of water onto the top of the melt pool is paramount to engender the development of a stable crust around the melt and therefore eliminating water ingression into melt pool and ensuring controlled coolability of the melt.
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      Experimental Investigation of Melt Coolability Behavior in an ExVessel Core Catcher: The Effect of Flooding Time

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    contributor authorV, Ganesh;Kulkarni, Parimal P.;Nayak, Arun K.
    date accessioned2023-04-06T12:59:26Z
    date available2023-04-06T12:59:26Z
    date copyright5/26/2022 12:00:00 AM
    date issued2022
    identifier issn23328983
    identifier otherners_008_03_031401.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4288885
    description abstractSome of the advanced nuclear reactors employ an exvessel core catcher to mitigate core melt scenarios by stabilizing and cooling the corium for a prolonged period by strategically flooding it. The side indirect cooling with top flooding strategy described in this study may lead to water ingression through the melt crust, which may lead to interaction between unoxidized metal and water, leading to hydrogen production. In order to avoid this deleterious scenario, water ingression into the interior region of the melt should be avoided. The studies described in this paper show that water ingression depends on the flooding strategy, i.e., the time delay between top flooding and melt relocation. Two experiments under identical conditions of simulant temperature, melt material, and test section geometry were conducted with simulated decay heat of 1 MW/m3. Sodium borosilicate glass was used as the corium simulant. In the first experiment, water was flooded onto the top of melt pool soon after melt relocation. In the second experiment, water flooding at the top of melt pool was made after 30 min of the melt relocation. The results show that a finite time delay of introduction of water onto the top of the melt pool is paramount to engender the development of a stable crust around the melt and therefore eliminating water ingression into melt pool and ensuring controlled coolability of the melt.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleExperimental Investigation of Melt Coolability Behavior in an ExVessel Core Catcher: The Effect of Flooding Time
    typeJournal Paper
    journal volume8
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4053220
    journal fristpage31401
    journal lastpage314017
    page7
    treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003
    contenttypeFulltext
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