STP514

    Relationship Between Charpy V and Fracture Mechanics KIc Assessments of A533-B Class 2 Pressure Vessel Steel

    Published: Jan 1972


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    Abstract

    A cooperative program between the Naval Research Laboratory and the Westinghouse Nuclear Energy Systems Division was established to explore possible relationships between postirradiation Charpy-V and fracture mechanics (KIc) data. Initial efforts centered on a 6 ⅜-in. AS33 grade B Class 2 steel plate for which the preirradiation condition had been well characterized by Charpy-V (Cv), tension, dynamic tear, and fracture mechanics tests. Low (<250 F, 121 C) temperature-high fluence exposure conditions were utilized to obtain large Cv, tensile and plane strain fracture toughness (KIc) property changes over the preirradiation condition.

    The simultaneous exposure of Cv and 1-in.-thick compact tension (CT) specimens produced comparable increases in Cv 30 ft ∙ lb transition temperature and KIc 65,000 psi √in. temperature. The Cv shelf energy was reduced from 74 to 46 ft ∙ lb. The postirradiation 75 F (24 C) yield strength was 127.3 ksi compared to a preirradiation value of 74.2 ksi; however, postirradiation yield strength decreased markedly with increasing temperature.

    The test capacity of the 1-in. CT specimen was found insufficient for ASTM valid KIc determinations at the Cv shelf level temperature for pre- or postirradiation conditions. The estimate of postirradiation KIc at Cv shelf temperatures would require a CT specimen thickness of at least 5 in. The data suggest that, if power reactor surveillance programs restrict test specimen size to a maximum of 1-in. thickness, and if the measuring capacity of CT specimens is the function of thickness described by ASTM, an empirical or correlation-projection approach would be required to utilize fracture mechanics specimens in such programs.

    Keywords:

    fracture (materials), fatigue (materials), fracture strength, impact tests, tension tests, fracture tests, irradiation, yield strength, stresses, cracks, pressure vessel steels


    Author Information:

    Hawthorne, JR
    Naval Research Laboratory, Washington, D.C.

    Mager, TR
    Nuclear Energy Systems, Westinghouse Electric Corp., Pittsburgh, Pa.


    Paper ID: STP38824S

    Committee/Subcommittee: E08.08

    DOI: 10.1520/STP38824S


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