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    A Procedure for the Assessment of the Structural Integrity of Nuclear Pressure Vessels

    Source: Journal of Pressure Vessel Technology:;1983:;volume( 105 ):;issue: 001::page 28
    Author:
    J. M. Bloom
    DOI: 10.1115/1.3264235
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents a simple engineering procedure that the utility industry can use to assess the integrity of typical nuclear-grade pressure vessels. The procedure recognizes both brittle fracture and plastic collapse and is based on a set of proposed failure assessment curves which make up a safety/failure plane. The plane is defined by the stress intensity factor/fracture toughness ratio as the ordinate and the applied stress/reference plastic collapse stress ratio as the abscissa. The failure assessment procedure is based in part on the British Central Electricity Generating Board’s R-6 failure assessment diagram and the deformation plasticity solutions of the General Electric Company. Two parameters, a plastic collapse parameter (Sr ′ ) and linear elastic fracture mechanics parameter (Kr ′ ) are calculated by the user. The point (Sr ′ , Kr ′ ) is plotted on the appropriate failure assessment diagram. If the point lies inside the respective curve, the structure is safe from failure. Moreover, for a given pressure and a postulated or actual flaw size, the margin of safety of the structure can be simply determined. Consistent with Appendix A of Section XI, (Division 1) of the ASME Boiler and Pressure Vessel Code the procedure presented in this paper is limited to ferritic materials 4 in. (102 mm) and greater in thickness. Details of the derivation of the proposed set of failure assessment curves are provided along with a sample problem illustrating the use of these curves.
    keyword(s): Pressure , Plasticity , Deformation , Fracture mechanics , Safety , Pressure vessels , Stress , Engineering processes and practices , ASME Boiler and Pressure Vessel Code , Brittle fracture , Collapse , Failure , Fracture toughness , Thickness AND Reactor vessels ,
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      A Procedure for the Assessment of the Structural Integrity of Nuclear Pressure Vessels

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    http://yetl.yabesh.ir/yetl1/handle/yetl/97551
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    contributor authorJ. M. Bloom
    date accessioned2017-05-08T23:16:21Z
    date available2017-05-08T23:16:21Z
    date copyrightFebruary, 1983
    date issued1983
    identifier issn0094-9930
    identifier otherJPVTAS-28218#28_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/97551
    description abstractThis paper presents a simple engineering procedure that the utility industry can use to assess the integrity of typical nuclear-grade pressure vessels. The procedure recognizes both brittle fracture and plastic collapse and is based on a set of proposed failure assessment curves which make up a safety/failure plane. The plane is defined by the stress intensity factor/fracture toughness ratio as the ordinate and the applied stress/reference plastic collapse stress ratio as the abscissa. The failure assessment procedure is based in part on the British Central Electricity Generating Board’s R-6 failure assessment diagram and the deformation plasticity solutions of the General Electric Company. Two parameters, a plastic collapse parameter (Sr ′ ) and linear elastic fracture mechanics parameter (Kr ′ ) are calculated by the user. The point (Sr ′ , Kr ′ ) is plotted on the appropriate failure assessment diagram. If the point lies inside the respective curve, the structure is safe from failure. Moreover, for a given pressure and a postulated or actual flaw size, the margin of safety of the structure can be simply determined. Consistent with Appendix A of Section XI, (Division 1) of the ASME Boiler and Pressure Vessel Code the procedure presented in this paper is limited to ferritic materials 4 in. (102 mm) and greater in thickness. Details of the derivation of the proposed set of failure assessment curves are provided along with a sample problem illustrating the use of these curves.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleA Procedure for the Assessment of the Structural Integrity of Nuclear Pressure Vessels
    typeJournal Paper
    journal volume105
    journal issue1
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.3264235
    journal fristpage28
    journal lastpage34
    identifier eissn1528-8978
    keywordsPressure
    keywordsPlasticity
    keywordsDeformation
    keywordsFracture mechanics
    keywordsSafety
    keywordsPressure vessels
    keywordsStress
    keywordsEngineering processes and practices
    keywordsASME Boiler and Pressure Vessel Code
    keywordsBrittle fracture
    keywordsCollapse
    keywordsFailure
    keywordsFracture toughness
    keywordsThickness AND Reactor vessels
    treeJournal of Pressure Vessel Technology:;1983:;volume( 105 ):;issue: 001
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
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