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    Pressure Suppression Containment Design—Current State of the Art

    Source: Journal of Engineering for Gas Turbines and Power:;1969:;volume( 091 ):;issue: 001::page 13
    Author:
    D. R. Miller
    DOI: 10.1115/1.3574667
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A summary of the thermodynamic design limits for pressure suppression containments for nuclear reactors is presented. Those parameters which must adhere to tested values are tabulated and discussed. An analytical model is described and is shown to accurately predict the existing test data. A graphical technique for predicting the transient peak containment pressure, based on the model, is presented for use in containment design.
    keyword(s): Pressure , Design , Containment AND Nuclear reactors ,
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      Pressure Suppression Containment Design—Current State of the Art

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    http://yetl.yabesh.ir/yetl1/handle/yetl/133545
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    contributor authorD. R. Miller
    date accessioned2017-05-09T00:19:36Z
    date available2017-05-09T00:19:36Z
    date copyrightJanuary, 1969
    date issued1969
    identifier issn1528-8919
    identifier otherJETPEZ-26673#13_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/133545
    description abstractA summary of the thermodynamic design limits for pressure suppression containments for nuclear reactors is presented. Those parameters which must adhere to tested values are tabulated and discussed. An analytical model is described and is shown to accurately predict the existing test data. A graphical technique for predicting the transient peak containment pressure, based on the model, is presented for use in containment design.
    publisherThe American Society of Mechanical Engineers (ASME)
    titlePressure Suppression Containment Design—Current State of the Art
    typeJournal Paper
    journal volume91
    journal issue1
    journal titleJournal of Engineering for Gas Turbines and Power
    identifier doi10.1115/1.3574667
    journal fristpage13
    journal lastpage20
    identifier eissn0742-4795
    keywordsPressure
    keywordsDesign
    keywordsContainment AND Nuclear reactors
    treeJournal of Engineering for Gas Turbines and Power:;1969:;volume( 091 ):;issue: 001
    contenttypeFulltext
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