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    Collapse Criterion for the CANDU 6 Calandria Vault Floor During a Severe Accident

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002::page 20908
    Author:
    David, Robert
    DOI: 10.1115/1.4035336
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The thickness at which the calandria vault floor in a generic CANDU 6 nuclear reactor may collapse while undergoing molten core–concrete interaction (MCCI) was studied using an approximate analytical model and a finite-element model. It was confirmed that the collapse criterion of 0.45 m floor thickness that is currently used in severe accident analyses is adequate. The estimated timing of collapse is subject to uncertainty of several hours.
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      Collapse Criterion for the CANDU 6 Calandria Vault Floor During a Severe Accident

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    https://yetl.yabesh.ir/yetl1/handle/yetl/4235303
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    contributor authorDavid, Robert
    date accessioned2017-11-25T07:18:39Z
    date available2017-11-25T07:18:39Z
    date copyright2017/1/3
    date issued2017
    identifier issn2332-8983
    identifier otherners_003_02_020908.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235303
    description abstractThe thickness at which the calandria vault floor in a generic CANDU 6 nuclear reactor may collapse while undergoing molten core–concrete interaction (MCCI) was studied using an approximate analytical model and a finite-element model. It was confirmed that the collapse criterion of 0.45 m floor thickness that is currently used in severe accident analyses is adequate. The estimated timing of collapse is subject to uncertainty of several hours.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleCollapse Criterion for the CANDU 6 Calandria Vault Floor During a Severe Accident
    typeJournal Paper
    journal volume3
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4035336
    journal fristpage20908
    journal lastpage020908-6
    treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002
    contenttypeFulltext
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