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    Fatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds

    Source: Journal of Engineering Materials and Technology:;1974:;volume( 096 ):;issue: 004::page 242
    Author:
    P. Shahinian
    ,
    H. E. Watson
    ,
    J. R. Hawthorne
    DOI: 10.1115/1.3443237
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Pre and postirradiation fatigue crack growth rates in A302-B, A533-B, and A543 steel plate and in two A543 welds (submerged arc and electroslag) were determined at 550 deg F (288 deg C) in air. The fracture mechanics approach was used to analyze the experimental data. Neutron irradiation at 585 deg F (307 deg C) to 2.5 × 1019 n/cm2 , > 1 MeV produced no significant effect on resistance to crack growth in A302-B steel and caused only a slight decrease in crack growth resistance of A533-B and A543 steels. Also, the resistance to crack growth of the submerged arc weld was unaffected by the irradiation, but that of the electroslag weld was substantially improved. The crack growth rate versus stress intensity factor range curve for the A302-B steel represents an upper bound for the pre and postirradiation data for the steels and welds of this study.
    keyword(s): Neutrons , Steel , Electrical resistance , Pressure vessels , Welded joints , Fatigue cracks , Fracture (Materials) , Irradiation (Radiation exposure) , Stress AND Fracture mechanics ,
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      Fatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/164786
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    contributor authorP. Shahinian
    contributor authorH. E. Watson
    contributor authorJ. R. Hawthorne
    date accessioned2017-05-09T01:38:10Z
    date available2017-05-09T01:38:10Z
    date copyrightOctober, 1974
    date issued1974
    identifier issn0094-4289
    identifier otherJEMTA8-26838#242_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/164786
    description abstractPre and postirradiation fatigue crack growth rates in A302-B, A533-B, and A543 steel plate and in two A543 welds (submerged arc and electroslag) were determined at 550 deg F (288 deg C) in air. The fracture mechanics approach was used to analyze the experimental data. Neutron irradiation at 585 deg F (307 deg C) to 2.5 × 1019 n/cm2 , > 1 MeV produced no significant effect on resistance to crack growth in A302-B steel and caused only a slight decrease in crack growth resistance of A533-B and A543 steels. Also, the resistance to crack growth of the submerged arc weld was unaffected by the irradiation, but that of the electroslag weld was substantially improved. The crack growth rate versus stress intensity factor range curve for the A302-B steel represents an upper bound for the pre and postirradiation data for the steels and welds of this study.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleFatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds
    typeJournal Paper
    journal volume96
    journal issue4
    journal titleJournal of Engineering Materials and Technology
    identifier doi10.1115/1.3443237
    journal fristpage242
    journal lastpage248
    identifier eissn1528-8889
    keywordsNeutrons
    keywordsSteel
    keywordsElectrical resistance
    keywordsPressure vessels
    keywordsWelded joints
    keywordsFatigue cracks
    keywordsFracture (Materials)
    keywordsIrradiation (Radiation exposure)
    keywordsStress AND Fracture mechanics
    treeJournal of Engineering Materials and Technology:;1974:;volume( 096 ):;issue: 004
    contenttypeFulltext
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