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    Introduction to Structural Failure Modes for Nuclear Power Facilities

    Source: Journal of Energy Engineering:;1993:;Volume ( 119 ):;issue: 002
    Author:
    John W. Reed
    ,
    Orhan Gurbuz
    DOI: 10.1061/(ASCE)0733-9402(1993)119:2(75)
    Publisher: American Society of Civil Engineers
    Abstract: This introduction provides a background of the evaluation methods for earthquakes larger than design basis. Seismic probabilistic risk assessment (SPRA) and seismic margin assessment (SMA) methods are introduced to the reader. The basic parameters used to define seismic capacity for each method are explained. The objectives of both evaluation methods and how they can be used to evaluate the adequacy of a seismic design are discussed. General issues related to computing seismic capacity are reviewed relative to SPRA and SMA. Four companion papers presented in the journal following this introduction discuss the types of information (i.e., dynamic tests, earthquake experience, and analytical data) that are used to determine the real capacity of structures and equipment in nuclear power plants to resist earthquakes. The motivation for discussing these three types of information is presented as an introduction to these papers that follow in this journal edition. The purpose of the present paper is to lay the groundwork and provide motivation for these papers.
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      Introduction to Structural Failure Modes for Nuclear Power Facilities

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    contributor authorJohn W. Reed
    contributor authorOrhan Gurbuz
    date accessioned2017-05-08T22:41:54Z
    date available2017-05-08T22:41:54Z
    date copyrightAugust 1993
    date issued1993
    identifier other%28asce%290733-9402%281993%29119%3A2%2875%29.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/86904
    description abstractThis introduction provides a background of the evaluation methods for earthquakes larger than design basis. Seismic probabilistic risk assessment (SPRA) and seismic margin assessment (SMA) methods are introduced to the reader. The basic parameters used to define seismic capacity for each method are explained. The objectives of both evaluation methods and how they can be used to evaluate the adequacy of a seismic design are discussed. General issues related to computing seismic capacity are reviewed relative to SPRA and SMA. Four companion papers presented in the journal following this introduction discuss the types of information (i.e., dynamic tests, earthquake experience, and analytical data) that are used to determine the real capacity of structures and equipment in nuclear power plants to resist earthquakes. The motivation for discussing these three types of information is presented as an introduction to these papers that follow in this journal edition. The purpose of the present paper is to lay the groundwork and provide motivation for these papers.
    publisherAmerican Society of Civil Engineers
    titleIntroduction to Structural Failure Modes for Nuclear Power Facilities
    typeJournal Paper
    journal volume119
    journal issue2
    journal titleJournal of Energy Engineering
    identifier doi10.1061/(ASCE)0733-9402(1993)119:2(75)
    treeJournal of Energy Engineering:;1993:;Volume ( 119 ):;issue: 002
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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