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    Prevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels

    Source: Journal of Pressure Vessel Technology:;1997:;volume( 119 ):;issue: 002::page 150
    Author:
    G. T. Yahr
    DOI: 10.1115/1.2842276
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Committee has approved rules for the use of 6061-T6 and 6061-T651 aluminum for the construction of Class 1 welded nuclear pressure vessels for temperatures not exceeding 149°C (300°F). Nuclear Code Case N-519 will allow the use of this aluminum in the construction of low-temperature research reactors such as the Advanced Neutron Source. The rules for protection against nonductile fracture are discussed. The basis for a value of 25.3 MPam (23 ksi in.) for the critical or reference stress intensity factor for use in the fracture analysis is presented. Requirements for consideration of the effects of neutron irradiation on the fracture toughness are discussed.
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      Prevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels

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    https://yetl.yabesh.ir/yetl1/handle/yetl/119269
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    contributor authorG. T. Yahr
    date accessioned2017-05-08T23:54:30Z
    date available2017-05-08T23:54:30Z
    date copyrightMay, 1997
    date issued1997
    identifier issn0094-9930
    identifier otherJPVTAS-28376#150_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/119269
    description abstractThe American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Committee has approved rules for the use of 6061-T6 and 6061-T651 aluminum for the construction of Class 1 welded nuclear pressure vessels for temperatures not exceeding 149°C (300°F). Nuclear Code Case N-519 will allow the use of this aluminum in the construction of low-temperature research reactors such as the Advanced Neutron Source. The rules for protection against nonductile fracture are discussed. The basis for a value of 25.3 MPam (23 ksi in.) for the critical or reference stress intensity factor for use in the fracture analysis is presented. Requirements for consideration of the effects of neutron irradiation on the fracture toughness are discussed.
    publisherThe American Society of Mechanical Engineers (ASME)
    titlePrevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels
    typeJournal Paper
    journal volume119
    journal issue2
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2842276
    journal fristpage150
    journal lastpage156
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;1997:;volume( 119 ):;issue: 002
    contenttypeFulltext
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