YaBeSH Engineering and Technology Library

    • Journals
    • PaperQuest
    • YSE Standards
    • YaBeSH
    • Login
    Search 
    •   YE&T Library
    • Search
    •   YE&T Library
    • Search
    • All Fields
    • Source Title
    • Year
    • Publisher
    • Title
    • Subject
    • Author
    • DOI
    • ISBN
    Advanced Search
    JavaScript is disabled for your browser. Some features of this site may not work without it.

    Search

    Show Advanced FiltersHide Advanced Filters

    Filters

    Use filters to refine the search results.

    Now showing items 1-8 of 8

    • Relevance
    • Title Asc
    • Title Desc
    • Year Asc
    • Year Desc
    • 5
    • 10
    • 20
    • 40
    • 60
    • 80
    • 100
  • Export
    • CSV
    • RIS
    • Sort Options:
    • Relevance
    • Title Asc
    • Title Desc
    • Issue Date Asc
    • Issue Date Desc
    • Results Per Page:
    • 5
    • 10
    • 20
    • 40
    • 60
    • 80
    • 100

    Further Observations on A533-B Steel Plate Tailored for Improved Radiation Embrittlement Resistance 

    Source: Journal of Pressure Vessel Technology:;1976:;volume( 098 ):;issue: 002:;page 111
    Author(s): J. R. Hawthorne
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A series of advanced investigations on the radiation performance of four 6-in-thick plates from a large (30-ton) commercial melt of A533-B steel is described. The melt represented the first ...
    Request PDF

    Radiation and Temper Embrittlement Processes in Advanced Reactor Weld Metals 

    Source: Journal of Manufacturing Science and Engineering:;1972:;volume( 094 ):;issue: 003:;page 807
    Author(s): J. R. Hawthorne; E. Fortner
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Experimental weld filler metals having high resistance to radiation embrittlement at ≃550 F (288 C) have been developed for quenched and tempered A543 and A542 steel. The filler metals are ...
    Request PDF

    Yankee Reactor Pressure Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined From Exposure During Cores II, III, and IV 

    Source: Journal of Fluids Engineering:;1967:;volume( 089 ):;issue: 004:;page 897
    Author(s): C. Z. Serpan; J. R. Hawthorne
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Charpy V-notch specimens representative of one of the several heats of A302-B steel forming the Yankee reactor pressure vessel, and irradiated as part of the Yankee surveillance program, have ...
    Request PDF

    Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels 

    Source: Journal of Fluids Engineering:;1967:;volume( 089 ):;issue: 001:;page 221
    Author(s): Charles Z. Serpan; L. E. Steele; J. R. Hawthorne
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The meaning and purpose of reactor pressure vessel surveillance is briefly discussed. Features of the surveillance programs in the Yankee, Big Rock Point, SM-1, and SM-1A reactors are briefly ...
    Request PDF

    Investigation of Warm Prestress for the Case of Small ΔT During a Reactor Loss-of-Coolant Accident 

    Source: Journal of Pressure Vessel Technology:;1979:;volume( 101 ):;issue: 004:;page 298
    Author(s): F. J. Loss; R. A. Gray; J. R. Hawthorne
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: An experimental investigation was conducted to characterize the benefits of warm prestress (WPS) in limiting crack extension in the wall of a nuclear vessel during a LOCA-ECCS. The present ...
    Request PDF

    A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance 

    Source: Journal of Fluids Engineering:;1971:;volume( 093 ):;issue: 002:;page 247
    Author(s): F. J. Loss; J. R. Hawthorne; C. Z. Serpan
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Fracture-safe operating criteria for commercial nuclear pressure vessels based on fracture analysis diagram procedures and Charpy-V energy trends are reappraised with respect to the effects of ...
    Request PDF

    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(s): P. Shahinian; H. E. Watson; J. R. Hawthorne
    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 ...
    Request PDF

    Analysis of Radiation-Induced Embrittlement Gradients on Fracture Characteristics of Thick-Walled Pressure Vessel Steels 

    Source: Journal of Manufacturing Science and Engineering:;1971:;volume( 093 ):;issue: 004:;page 1007
    Author(s): F. J. Loss; J. R. Hawthorne; C. Z. Serpan; P. P. Puzak
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The fracture behavior of thick-walled nuclear vessels is considered for the case of a radiation-induced toughness gradient through the wall which characteristically results from neutron attenuation ...
    Request PDF
    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian
     

    Author

    Publisher

    Year

    Type

    Content Type

    Publication Title

    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian