STP380: The Use of Materials Properties by the Reactor Vessel Designer

    Langer, B. F.
    Consulting engineer, Bettis Atomic Power Laboratory, Westinghouse Electric Corp., Pittsburgh, Pa.

    Pages: 11    Published: Jan 1965


    Abstract

    This paper discusses the information which the pressure vessel designer must obtain from the materials engineer in order to provide protection against crack growth and brittle fracture. The most meaningful fatigue tests in the low-cycle range are those in which strain, rather than stress, is the controlled parameter. Therefore, many fatigue data in the literature are of little use to the pressure vessel designer and new tests will be needed. The subject of fatigue notch sensitivity is a very important one which requires further investigation. The correlation between fatigue properties, strength properties, and ductility is of particular interest because the principal effects of neutron bombardment are to increase the strength and lower the ductility. Irradiation also raises the transition temperature, meaning that the reactor vessel designer must consider the possibility of brittle fracture occurring late in life.


    Paper ID: STP43543S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP43543S


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