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    Extensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinder

    Source: Journal of Pressure Vessel Technology:;1985:;volume( 107 ):;issue: 001::page 25
    Author:
    J. M. Bloom
    DOI: 10.1115/1.3264399
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A simple, viable engineering method for assessing the integrity of nuclear pressure vessels has been developed at Babcock & Wilcox. The method uses results given in a plastic fracture handbook developed by General Electric and which are in the format of the Central Electricity Generation Board of the United Kingdom R-6 failure assessment diagram. The method is currently limited to two-dimensional/axisymmetric structural models with continuous flaws. Failure assessment of nuclear pressure vessels with assumed continuous flaws result in the calculation of overly conservative safety margins. This paper presents the extension of the existing failure assessment approach to include semi-elliptical flaw models, as well as example problems which demonstrate increased safety margins over the continuous flaw assumptions. In particular, failure assessment diagram curves and the corresponding failure assessment point expressions for an axially cracked pressurized cylinder with an ASME Section III, Appendix G semi-elliptical flaw are presented. The results of the example problems considering the less conservative semi-elliptical flaw model versus the continuous flaw model dramatically illustrate increased safety margins of 50 percent when more realistic semi-elliptical flaws are postulated. The results given in this paper are particularly valuable in the safety assessment of PWR vessels which have low toughness welds in their beltline regions.
    keyword(s): Cylinders , Failure , Safety , Reactor vessels , Pressurized water reactors , Toughness , Vessels , Welded joints , Fracture (Process) AND Electric power generation ,
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      Extensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinder

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    http://yetl.yabesh.ir/yetl1/handle/yetl/100315
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    contributor authorJ. M. Bloom
    date accessioned2017-05-08T23:21:02Z
    date available2017-05-08T23:21:02Z
    date copyrightFebruary, 1985
    date issued1985
    identifier issn0094-9930
    identifier otherJPVTAS-28251#25_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/100315
    description abstractA simple, viable engineering method for assessing the integrity of nuclear pressure vessels has been developed at Babcock & Wilcox. The method uses results given in a plastic fracture handbook developed by General Electric and which are in the format of the Central Electricity Generation Board of the United Kingdom R-6 failure assessment diagram. The method is currently limited to two-dimensional/axisymmetric structural models with continuous flaws. Failure assessment of nuclear pressure vessels with assumed continuous flaws result in the calculation of overly conservative safety margins. This paper presents the extension of the existing failure assessment approach to include semi-elliptical flaw models, as well as example problems which demonstrate increased safety margins over the continuous flaw assumptions. In particular, failure assessment diagram curves and the corresponding failure assessment point expressions for an axially cracked pressurized cylinder with an ASME Section III, Appendix G semi-elliptical flaw are presented. The results of the example problems considering the less conservative semi-elliptical flaw model versus the continuous flaw model dramatically illustrate increased safety margins of 50 percent when more realistic semi-elliptical flaws are postulated. The results given in this paper are particularly valuable in the safety assessment of PWR vessels which have low toughness welds in their beltline regions.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleExtensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinder
    typeJournal Paper
    journal volume107
    journal issue1
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.3264399
    journal fristpage25
    journal lastpage29
    identifier eissn1528-8978
    keywordsCylinders
    keywordsFailure
    keywordsSafety
    keywordsReactor vessels
    keywordsPressurized water reactors
    keywordsToughness
    keywordsVessels
    keywordsWelded joints
    keywordsFracture (Process) AND Electric power generation
    treeJournal of Pressure Vessel Technology:;1985:;volume( 107 ):;issue: 001
    contenttypeFulltext
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