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    STP341

    Effect of Neutron Irradiation at 550 F on Charpy Impact Properties of ASTM A 302 Grade B Steel

    Published: 01 January 1963


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    Abstract

    Test data are presented from the first three sets of a series of V-notch Charpy impact specimens irradiated with neutrons in the Dresden Nuclear Power Reactor to measure the mechanical property changes of the pressure vessel steel. A number of groups of impact specimens were machined from the actual reactor pressure vessel steel, ASTM Specification A 302 grade B plate. They were placed, in sealed capsules, in the interior of the reactor pressure vessel where they were exposed to intense neutron irradiation at 545 F, the operating temperature of the reactor. Impact transition curves were determined on four groups of specimens covering a range of neutron exposure from 0 to 1019 nvt > 1 Mev. Based on the 30 ft-lb transition, the maximum increase in transition temperature measured was 150 F. Additional impact specimens are being irradiated in the reactor and will be removed periodically and tested over a 30-yr period.


    Author Information:

    Brandt, F. A.
    General Electric Co., San Jose, Calif.

    Alexander, A. J.
    AVCO Corp., Stratford, Conn.


    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP41752S