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    Reactor Coolant Pump Flywheel Overspeed Evaluation

    Source: Journal of Pressure Vessel Technology:;1974:;volume( 096 ):;issue: 004::page 279
    Author:
    P. C. Riccardella
    ,
    W. H. Bamford
    DOI: 10.1115/1.3454182
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The overspeed capability of the large steel flywheels used on light water reactor primary coolant pumps has been evaluated through a combined analytical and experimental effort. Limiting speeds of the prototype flywheel design were calculated for the ductile failure mode using the principles of Section III of the ASME Boiler and Pressure Vessel Code, and for the brittle fracture mode using a fracture mechanics approach in which stress intensity factors were determined from finite element computer analysis. The accuracy of the analytical approach was verified by a scale model test program which demonstrates excellent agreement between experiment and analysis. The results of the evaluation are presented in this paper, and they illustrate the kinds of things which can be accomplished through application of modern fracture mechanics technology, including plasticity considerations, to the solution of hardware problems of real engineering interest.
    keyword(s): Flywheels , Pumps , Nuclear reactor coolants , Fracture mechanics , Steel , Hardware , Stress , Coolants , Engineering prototypes , Design , Finite element analysis , Light water reactors , Plasticity , Computers , ASME Boiler and Pressure Vessel Code , Brittle fracture AND Failure ,
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      Reactor Coolant Pump Flywheel Overspeed Evaluation

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    http://yetl.yabesh.ir/yetl1/handle/yetl/165182
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    contributor authorP. C. Riccardella
    contributor authorW. H. Bamford
    date accessioned2017-05-09T01:38:54Z
    date available2017-05-09T01:38:54Z
    date copyrightNovember, 1974
    date issued1974
    identifier issn0094-9930
    identifier otherJPVTAS-28112#279_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/165182
    description abstractThe overspeed capability of the large steel flywheels used on light water reactor primary coolant pumps has been evaluated through a combined analytical and experimental effort. Limiting speeds of the prototype flywheel design were calculated for the ductile failure mode using the principles of Section III of the ASME Boiler and Pressure Vessel Code, and for the brittle fracture mode using a fracture mechanics approach in which stress intensity factors were determined from finite element computer analysis. The accuracy of the analytical approach was verified by a scale model test program which demonstrates excellent agreement between experiment and analysis. The results of the evaluation are presented in this paper, and they illustrate the kinds of things which can be accomplished through application of modern fracture mechanics technology, including plasticity considerations, to the solution of hardware problems of real engineering interest.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleReactor Coolant Pump Flywheel Overspeed Evaluation
    typeJournal Paper
    journal volume96
    journal issue4
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.3454182
    journal fristpage279
    journal lastpage285
    identifier eissn1528-8978
    keywordsFlywheels
    keywordsPumps
    keywordsNuclear reactor coolants
    keywordsFracture mechanics
    keywordsSteel
    keywordsHardware
    keywordsStress
    keywordsCoolants
    keywordsEngineering prototypes
    keywordsDesign
    keywordsFinite element analysis
    keywordsLight water reactors
    keywordsPlasticity
    keywordsComputers
    keywordsASME Boiler and Pressure Vessel Code
    keywordsBrittle fracture AND Failure
    treeJournal of Pressure Vessel Technology:;1974:;volume( 096 ):;issue: 004
    contenttypeFulltext
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