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    Quantitative Prediction of EAC Crack Growth Rate of Sensitized Type 304 Stainless Steel in Boiling Water Reactor Environments Based on EPFEM

    Source: Journal of Pressure Vessel Technology:;2007:;volume( 129 ):;issue: 003::page 460
    Author:
    He Xue
    ,
    Tetsuo Shoji
    DOI: 10.1115/1.2748827
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The quantitative prediction of environmentally assisted cracking (EAC) or stress corrosion cracking (SCC) is essential in order to predict service life and also the structural integrity and safety assessment of light water reactors. During the last 3 decades many of the research results obtained on the quantitative prediction of the EAC crack growth rate have been based on linear fracture mechanics. In order to investigate EAC behavior in the high strain zone of important structures in light water reactors, the approach taken in this paper is one in which quantitative calculations of the EAC crack growth rate, incorporating the SCC deformation /oxidation model and the elastic-plastic finite element method (EPFEM), are carried out. This approach can be used for the quantitative prediction of EAC crack growth rate in both the low and high strain zones of key structures in light water reactors. The crack growth behavior of sensitized type 304 stainless steel with a 1T-CT specimen in simulated boiling water reactor (BWR) environments is analyzed based on this approach. The effect of several environmental, material, and mechanical parameters on the EAC crack growth rate of nickel based alloys in high-temperature aqueous environments is also discussed.
    keyword(s): Fracture (Materials) , Stainless steel , Boiling water reactors AND Water ,
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      Quantitative Prediction of EAC Crack Growth Rate of Sensitized Type 304 Stainless Steel in Boiling Water Reactor Environments Based on EPFEM

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    http://yetl.yabesh.ir/yetl1/handle/yetl/136694
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    contributor authorHe Xue
    contributor authorTetsuo Shoji
    date accessioned2017-05-09T00:25:31Z
    date available2017-05-09T00:25:31Z
    date copyrightAugust, 2007
    date issued2007
    identifier issn0094-9930
    identifier otherJPVTAS-28483#460_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/136694
    description abstractThe quantitative prediction of environmentally assisted cracking (EAC) or stress corrosion cracking (SCC) is essential in order to predict service life and also the structural integrity and safety assessment of light water reactors. During the last 3 decades many of the research results obtained on the quantitative prediction of the EAC crack growth rate have been based on linear fracture mechanics. In order to investigate EAC behavior in the high strain zone of important structures in light water reactors, the approach taken in this paper is one in which quantitative calculations of the EAC crack growth rate, incorporating the SCC deformation /oxidation model and the elastic-plastic finite element method (EPFEM), are carried out. This approach can be used for the quantitative prediction of EAC crack growth rate in both the low and high strain zones of key structures in light water reactors. The crack growth behavior of sensitized type 304 stainless steel with a 1T-CT specimen in simulated boiling water reactor (BWR) environments is analyzed based on this approach. The effect of several environmental, material, and mechanical parameters on the EAC crack growth rate of nickel based alloys in high-temperature aqueous environments is also discussed.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleQuantitative Prediction of EAC Crack Growth Rate of Sensitized Type 304 Stainless Steel in Boiling Water Reactor Environments Based on EPFEM
    typeJournal Paper
    journal volume129
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2748827
    journal fristpage460
    journal lastpage467
    identifier eissn1528-8978
    keywordsFracture (Materials)
    keywordsStainless steel
    keywordsBoiling water reactors AND Water
    treeJournal of Pressure Vessel Technology:;2007:;volume( 129 ):;issue: 003
    contenttypeFulltext
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