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    Trial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct

    Source: Journal of Pressure Vessel Technology:;1981:;volume( 103 ):;issue: 004::page 380
    Author:
    V. K. Sazawal
    DOI: 10.1115/1.3263417
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents the results of a comprehensive trial application of the draft structural design criteria for highly irradiated core components to a typical blanket assembly duct. The development of the criteria (proposed RDT F 9-7) is sponsored by the U.S. Department of Energy. The activity focuses on the evaluation of the criteria using a typical breeder reactor blanket assembly as a test case and is not intended for judging the adequacy of the component design. Pertinent design rules from the draft criteria are applied to the component to determine: (a) difficulties, if any, that may arise in interpretation and application of the criteria, and (b) adequacy of the criteria rules and analysis methods to address various potential failure mechanisms expected in the reactor core during service. Based on the trial application, various recommendations are made to promote further development of the criteria.
    keyword(s): Structural design , Manufacturing , Ducts , Breeder reactors , Design AND Failure mechanisms ,
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      Trial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct

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    https://yetl.yabesh.ir/yetl1/handle/yetl/95015
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    contributor authorV. K. Sazawal
    date accessioned2017-05-08T23:11:56Z
    date available2017-05-08T23:11:56Z
    date copyrightNovember, 1981
    date issued1981
    identifier issn0094-9930
    identifier otherJPVTAS-28204#380_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/95015
    description abstractThis paper presents the results of a comprehensive trial application of the draft structural design criteria for highly irradiated core components to a typical blanket assembly duct. The development of the criteria (proposed RDT F 9-7) is sponsored by the U.S. Department of Energy. The activity focuses on the evaluation of the criteria using a typical breeder reactor blanket assembly as a test case and is not intended for judging the adequacy of the component design. Pertinent design rules from the draft criteria are applied to the component to determine: (a) difficulties, if any, that may arise in interpretation and application of the criteria, and (b) adequacy of the criteria rules and analysis methods to address various potential failure mechanisms expected in the reactor core during service. Based on the trial application, various recommendations are made to promote further development of the criteria.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleTrial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct
    typeJournal Paper
    journal volume103
    journal issue4
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.3263417
    journal fristpage380
    journal lastpage387
    identifier eissn1528-8978
    keywordsStructural design
    keywordsManufacturing
    keywordsDucts
    keywordsBreeder reactors
    keywordsDesign AND Failure mechanisms
    treeJournal of Pressure Vessel Technology:;1981:;volume( 103 ):;issue: 004
    contenttypeFulltext
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