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    Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels

    Source: Journal of Fluids Engineering:;1967:;volume( 089 ):;issue: 001::page 221
    Author:
    Charles Z. Serpan
    ,
    L. E. Steele
    ,
    J. R. Hawthorne
    DOI: 10.1115/1.3609556
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The meaning and purpose of reactor pressure vessel surveillance is briefly discussed. Features of the surveillance programs in the Yankee, Big Rock Point, SM-1, and SM-1A reactors are briefly described along with results of testing metallurgical specimens from these programs. Additionally, the surveillance program to be effected in the Army MH-1A reactor is described. Certain problems which have occurred in the course of these programs are discussed as well as the proposed ASTM recommendations for radiation-damage surveillance programs. The value of these programs to reactor operators is reviewed with relation to the results obtained to date.
    keyword(s): Radiation (Physics) , Surveillance , Reactor vessels , Army , ASTM International , Testing AND Rocks ,
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      Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/120701
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    • Journal of Fluids Engineering

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    contributor authorCharles Z. Serpan
    contributor authorL. E. Steele
    contributor authorJ. R. Hawthorne
    date accessioned2017-05-08T23:57:06Z
    date available2017-05-08T23:57:06Z
    date copyrightMarch, 1967
    date issued1967
    identifier issn0098-2202
    identifier otherJFEGA4-27291#221_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/120701
    description abstractThe meaning and purpose of reactor pressure vessel surveillance is briefly discussed. Features of the surveillance programs in the Yankee, Big Rock Point, SM-1, and SM-1A reactors are briefly described along with results of testing metallurgical specimens from these programs. Additionally, the surveillance program to be effected in the Army MH-1A reactor is described. Certain problems which have occurred in the course of these programs are discussed as well as the proposed ASTM recommendations for radiation-damage surveillance programs. The value of these programs to reactor operators is reviewed with relation to the results obtained to date.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleFeatures and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels
    typeJournal Paper
    journal volume89
    journal issue1
    journal titleJournal of Fluids Engineering
    identifier doi10.1115/1.3609556
    journal fristpage221
    journal lastpage232
    identifier eissn1528-901X
    keywordsRadiation (Physics)
    keywordsSurveillance
    keywordsReactor vessels
    keywordsArmy
    keywordsASTM International
    keywordsTesting AND Rocks
    treeJournal of Fluids Engineering:;1967:;volume( 089 ):;issue: 001
    contenttypeFulltext
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