In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel

    Published: Jan 1965

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    This paper describes an experimental irradiation assembly and associated instrumentation which has been developed and successfully utilized for the performance of dynamic, in-reactor low cycle fatigue tests of reactor pressure vessel steels. The equipment provides for the simultaneous reverse bend testing of as many as 15 sheet-type specimens representing a range of strain amplitudes at controlled temperatures in the range of 300 to 700 F.

    The results of an exploratory investigation on the fatigue resistance of ASTM A302-B steel during irradiation at 500 F are presented and compared with data from out-of-reactor control tests.

    Author Information:

    Hawthorne, J. R.
    Heads, U. S. Naval Research Laboratory, Washington, D. C.

    Steele, L. E.
    Heads, U. S. Naval Research Laboratory, Washington, D. C.

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP43539S

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