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    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 ...
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    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 ...
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    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 ...
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